US 20020031200 A1
A method for controlling vessel chemistry in a boiling water reactor (BWR) includes a targeted injection of hydrazine (N2H4) to overcome intergranular stress corrosion cracking (IGSCC) and provide other advantages. The method does not require the injection of hydrogen as a reducing species nor the costly equipment needed to store and control the injection of hydrogen, but it is optional. The method involves: 1) adding a carefully selected amount of N2H4 at a carefully selected location such that reaction with hydrogen peroxide (H2O2) is targeted for reduction prior to treated vessel water (feed water combined with steam dryer/separator liquid effluent) entering the reactor core and 2) providing sufficient residence time to keep all but a tolerable amount of the N2H4 from entering the reactor core. The method may also include the steps of: 1) examining vessel water upstream of the reactor core to assess the type and amount of N2H4 fragments and 2) calculating and/or externally measuring electrochemical corrosion potential (ECP) from the type and amount of N2H4 fragments. That is, the injection of N2H4 may be used to control in-vessel chemistry, but can also be used as a tool to monitor vessel chemistry and determine vessel ECP.
1. A method for controlling vessel chemistry of a boiling water reactor (BWR), comprising the steps of:
adding a sufficient amount of N2H4 at an effective location to react with H2O2 and to reduce an initial amount of H2O2 to a desired amount in vessel water entering a reactor core; and
providing a sufficient residence time to consume all but a tolerable amount of the added N2H4 prior to the vessel water entering a reactor core.
2. The method of
determining the initial amount of H2O2 in liquid effluent returned for combination with the feed water; and
selecting the sufficient amount of N2H4 at least partially based upon the initial amount of H2O2 in the liquid effluent.
3. The method of
4. The method of
5. The method of
6. The method of
7. The method of
8. The method of
9. The method of
10. The method of
11. The method of
12. The method of
13. The method of
14. The method of
examining vessel water upstream of the reactor core to assess the type and amount of N2H4 fragments; and
calculating electrochemical corrosion potential from the type and amount of N2H4 fragments.
15. The method of
collecting a sample of vessel water upstream of the reactor core; and
obtaining a complete assessment of vessel chemistry by analyzing the sample only for the presence of components other than H2O2.
16. A method for controlling vessel chemistry of a boiling water reactor (BWR), comprising the steps of:
determining the initial amount of H2O2 in liquid effluent returned for combination with feed water;
adding a sufficient amount of N2H4, as selected at least partially based upon the initial amount of H2O2 in the liquid effluent, at an effective location to react with H2O2 and to reduce an initial amount of H2O2 to a desired amount in vessel water entering a reactor core; and
providing a sufficient residence time to consume all but a tolerable amount of the added N2H4 prior to the vessel water entering a reactor core.
17. The method of
18. The method of
19. The method of
20. A method for controlling vessel chemistry of a boiling water reactor (BWR), comprising the steps of:
adding a sufficient amount of N2H4 at an effective location to react with H2O2 and to reduce an initial amount of H2O2 to a desired amount in vessel water entering a reactor core;
providing a sufficient residence time to consume all but a tolerable amount of the added N2H4 prior to the vessel water entering a reactor core;
examining vessel water upstream of the reactor core to assess the type and amount of N2H4 fragments; and
calculating electrochemical corrosion potential from the type and amount of N2H4 fragments.
21. A method of controlling reaction vessel chemistry of a boiling water reactor (BWR) having a feed water flow stream entering a reaction vessel, the method comprising the steps of:
calculating an amount of N2H4 necessary to consume at least a majority of an amount of H2O2 in a fluid of the BWR;
injecting at least a portion of the calculated amount of N2H4 into the feed water flow stream; and
evaluate whether the injected N2H4 consumed the majority of the amount of H2O2 in a fluid of the BWR.
22. The method of
determining an amount of H2O2 in the fluid of the BWR;
determining an amount of H2O2 to remain in the fluid of the BWR; and
calculating the amount of N2H4 necessary to consume all but the amount of H2O2 to remain in the fluid of the BWR.
23. The method of
evaluating the ECP; and
reducing the determined amount of H2O2 to remain until the ECP is less than or equal to −230 mev.
24. The method of
25. The method of
calculating a duration of time during which the amount of N2H4 will react with the H2O2; and
adjusting the calculated amount of N2H4 necessary in accordance with the duration of time.
26. The method of
27. The method of
repeatedly injecting the portion of the calculated amount of N2H4 into the feed water flow stream;
monitoring at least one of a main steam line radiation dose rate, an advanced offgas system offgas, a reactor water cleanup, and an ECP to evaluate the effectiveness of the N2H4 injection.
28. The method of
29. The method of
determining an amount of catalyst to enhance the consumption of the majority of the amount of H2O2;
adding the amount catalyst to the feed water flow stream; and
adjusting the calculated amount of N2H4 in accordance with the added catalyst.
30. The method of
 1. Technical Field
 This invention relates to the field of boiling water reactors. More specifically, the invention relates to a method for controlling boiling water reactor vessel chemistry.
 2. Background Art
 The current world population has developed a high level of dependence on electric power and a variety of systems are available for generating the vast amounts of electric power currently required. Nuclear reactors are one well known system for generating electric power. In one type of nuclear reactor, a boiling water reactor (BWR), vessel water is heated in a reactor core where nuclear fission occurs and the resulting steam is used to turn turbines for electric power generation. To avoid damage to the turbines, steam generated from the reactor core is dried inside the BWR vessel in a steam separator and steam dryer and the collected water (liquid effluent) is returned for reheating to the reactor core without leaving the BWR vessel. The dried steam sent to the turbines ultimately condenses and is returned as feed water to the BWR vessel where it is combined with the steam dryer/separator liquid effluent to form vessel water that is subsequently reheated in the reactor core.
 The materials used in a BWR are carefully selected to withstand, as much as possible, the conditions within the BWR vessel. Nevertheless, intergranular stress corrosion cracking (IGSCC) is a known phenomenon that occurs in the various components of a BWR. The causes and effects of IGSCC are well documented in numerous technical and patent references. Prior attempts to remedy IGSCC are disclosed in the following U.S. patents that are herein incorporated by reference: U.S. Pat. Nos. 5,135,709, 5,608,766 and 5,581,588 issued to Andresen et al., U.S. Pat. No. 4,430,293 issued to Callaghan et al., U.S. Pat. No. 4,842,811 issued to Desilva, U.S. Pat. Nos. 5,473,646 and 5,301,271 issued to Heck et al., U.S. Pat. No. 5,287,392 issued to Cowan II, et al., U.S. Pat. No. 5,130,079 issued to Chakraborty, U.S. Pat. No. 5,164,152 issued to Kim et al., U.S. Pat. Nos. 5,130,081 and 5,130,080 issued to Niedrach, U.S. Pat. Nos. 5,602,888, 5,600,692, 5,600,691, and 5,448,605 issued to Hettiarachchi et al.
 As discussed in the above listed references and in a wide variety of other references, the primary causative agent focused on in IGSCC studies is oxygen produced from the radiolytic decomposition of water when subjected to irradiation in the reactor core. The presence of the excess dissolved oxygen in the heated water creates an electrochemical corrosion potential (ECP) which will result in increasing IGSCC attack as the ECP increases (e.g. becomes more positive). While other oxidizing species, such as hydrogen peroxide are produced from radiolytic decomposition of water, very strong emphasis has been placed on providing reducing species to combine specifically with oxygen and thus reduce the ECP. While attempts have been made at using ammonia and hydrazine as reducing species in a test reactor core, serious disadvantages of these reducing species became readily apparent. Accordingly, hydrogen is universally accepted as the reducing species of choice in a BWR. The hydrogen is generally injected into feed water which then enters the BWR vessel. By providing an excess amount of hydrogen in the vessel water of a BWR, the equilibrium of the hydrogen-oxygen recombination reaction is shifted to encourage conversion of oxygen as an oxidizing species to water.
 Unfortunately, there are several widely recognized disadvantages of using hydrogen as a reducing agent, even though hydrogen is the most preferred reducing agent. First, a relatively large amount of gaseous hydrogen must be maintained near the BWR creating a potential industrial hazard since hydrogen is highly flammable. Second, hydrogen gas must be added continuously in small amounts that are potentially difficult to control in transient operation. The amount of hydrogen directly affects the radiation dose in steam lines supplying steam to the turbines from the carryover of radioactive nitrogen 16 (N16) in the form of ammonia that is generated in the reactor core. Variations in the flow of feed water and/or hydrogen addition may cause spikes in the concentration of hydrogen and resulting spikes in radiation dose in steam lines or large variations in ECP. Third, although known as an oxygen scavenger, hydrogen recombination with oxygen is typically considered “sluggish” in BWR reactor environments. The inefficiency of the recombination reaction encourages injection of more hydrogen than is theoretically needed. This excess hydrogen tends to form volatile ammonia with highly radioactive N16 in the reactor core, and causes increased steam line dose rates when the N16 ammonia exits the reactor. Fourth, the only presently available hydrogen injection system is very costly.
 Given the problems associated with hydrogen as a reducing species, various catalytic processes have been proposed for use in a BWR to enhance the hydrogen- oxygen recombination reaction. While several systems are described in the above referenced patents, perhaps the most promising to date involves treating the BWR vessel and vessel components with a chemical catalyst including platinum and rhodium in a soluble liquid form. The catalyst is applied when the reactor is about to shut down for fuel reloading and is predicted to last through the next fuel cycle. By mechanically bonding to the vessel and vessel components, the catalyst promotes recombination of oxygen with hydrogen rather than combination of oxygen with iron or other elements in stainless steel components that causes corrosion. Using the catalyst along with hydrogen injection, as described above, reduces the amount of hydrogen needed and produces fewer side effects than hydrogen injection alone. Nevertheless, the cost of the catalyst is extremely high as is the instrumentation used to monitor the effectiveness of the catalyst system.
 Thus, it can be seen that there exists a need to provide a method for controlling IGSCC that reduces the hazards, costs, and instabilities of present methods, such as hydrogen injection and/or catalytic recombination. Without such improved methods, electric utilities operating nuclear reactors will continue to face the current unfavorable and costly circumstances involved in controlling IGSCC.
 According to the present invention, a method for controlling vessel chemistry of a boiling water reactor (BWR) is provided that does not require the injection of hydrogen as a reducing species nor the costly equipment needed to store and control the injection of hydrogen. The method includes the steps of: 1) adding hydrazine (N2H4) to react with hydrogen peroxide (H2O2) in a BWR and to reduce the amount of H2O2 to a desired amount in vessel water that enters the reactor core and 2) providing a sufficient residence time to consume all but a tolerable amount of the added N2H4 prior to the vessel water entering the reactor core.
 By way of example, the method may further include the steps of: 1) determining the amount of H2O2 in steam dryer/separator liquid effluent and 2) selecting the amount of N2H4 at least partially based upon the determined amount of H2O2 in the liquid effluent. If the H2O2 can be reduced to less than approximately 5 part per billion (ppb) (mass) in vessel water entering the reactor core, several advantages are obtained. First, the environment causing intergranular stress corrosion cracking (IGSCC) is made less oxidizing and more reducing, thus protecting (in part or in full) components downstream where H2O2 is reduced. If accomplished rapidly, much less ammonia containing N1″ (radioactive nitrogen) is produced in the reactor core compared to when hydrogen is used as a reducing species. Further, while N2H4 is relatively costly to purchase, the equipment needed for handling and injecting N2H4 into the BWR is conventional industrial equipment that is much less costly than hydrogen injection equipment. Additionally, by reducing the amount of H2O2, samples of vessel water entering the reactor core may be collected and analyzed by conventional testing without concern for misrepresentation of water chemistry from decomposition of unstable H2O2 species in the collected sample. Without such capability, very costly in-vessel probes and associated analyzing equipment would be required to accurately represent water chemistry of the vessel water entering the reactor core.
 Several control scenarios are conceivable when using the present method. For example, first, the amounts of N2H4 selected for injection may be targeted to only partially reduce the amount of H2O2 in vessel water. Second, the amount of N2H4 selected may be sufficient to reduce H2O2 to less than approximately 5 ppb, without affecting the presence of oxygen (O2). Third, the amount of N2H4 added may be sufficient to reduce H2O2 to below approximately 5 ppb and also affect the amount of O2 present by reducing it as much as possible while still consuming all but a tolerable amount of the added N2H4 prior to vessel water entering the reactor core. Fourth, since some BWRs may be less sensitive to the byproducts produced when N2H4 decomposes in the reactor core, consuming all but a tolerable amount of the added N2H4 may leave behind a relatively large amount of N2H4 when compared to the amount of N2H4 that may be tolerated in another BWR system. For most BWR systems, consuming all but a tolerable amount requires consuming substantially all of the N2H4, for example, approximately 5 ppb or less.
 The effectiveness of the N2H4 injection can be modified depending upon the location of the injection. One example of a preferred location is injecting N2H4 in the feed water line upstream of feed water spargers such that N2H4 laden feed water is applied to returned steam dryer/separator liquid effluent in the BWR mixing plenum. Also, reaction of N2H4 with H2O2 may be enhanced by providing a catalyst. For example, ionic copper (Cu2+ ) acts as a catalyst for this reaction and may be present in the feed water of some BWR systems. Further, the method described above may also be used in conjunction with a noble metal catalyst promoting combination of hydrogen and oxygen and/or additionally injecting excess hydrogen to promote such recombination. Accordingly, while N2H4 injection may be used alone to control vessel chemistry of a BWR, it is compatible with the simultaneous use of conventional methods for controlling vessel chemistry and may be used in combination therewith.
 Finally, the present method may also include the steps of: 1) examining vessel water upstream of the reactor core to assess the type and amount of N2H4 fragments and 2) calculating and/or externally measuring electrochemical corrosion potential (ECP) from the type and amount of N2H4 fragments (nitrogen, ammonium hydroxide, and unreacted hydrazine, where ammonium hydroxide is the water soluble form of ammonia). That is, the injection of N2H4 may be used to control in-vessel chemistry, but can also be used as a tool to monitor vessel chemistry and determine vessel ECP. Such a method thus enables a straight forward mechanism for ensuring that proper protection of the vessel and vessel components is provided.
 The foregoing and other features and advantages of the present invention will be apparent from the following more particular description of preferred embodiments of the invention, as illustrated in the accompanying drawings.
 Preferred embodiments of the present invention will hereinafter be described in conjunction with the appended drawings, where like designations denote like elements, and:
FIG. 1 is a flow diagram of a method according to a preferred embodiment of the present invention;
FIG. 2 is a flow diagram of boiling water reactor system according to a preferred embodiment of the present invention;
FIG. 3 is a more detailed flow diagram of the reactor vessel in FIG. 2; and
FIG. 4 is a chart of electrochemical corrosion potential as a function of hydrazine injection concentration.
 According to a preferred embodiment of the present invention, a method for controlling vessel chemistry in a boiling water reactor (BWR) is provided that uses a targeted injection of hydrazine (N2H4) to overcome the various problems with conventional methods for reducing intergranular stress corrosion cracking (IGSCC) and providing other new advantages. In particular, the method reduces electrochemical corrosion potential (ECP) in a BWR. The method does not require the injection of hydrogen as a reducing species nor the costly equipment needed to store and control the injection of hydrogen, but it is optional. The method involves: 1) adding a carefully selected amount of N2H4 at a carefully selected location such that reaction with hydrogen peroxide (H2O2) is targeted for reduction prior to treated vessel water (feed water combined with steam dryer/separator liquid effluent) entering the reactor core and 2) providing sufficient residence time to keep all but a tolerable amount of the N2H4 from entering the reactor core. The targeted reaction is N2H4+2H2O2→N2+4H2O. While N2H4 is known as a reducing species for nuclear reactor feed water and H2O2 is known as an oxidizing species, it is not known to select the amount of N2H4 added and the injection location such that reaction with H2O2 is targeted. N2H4 has been traditionally assumed to be ineffective in a BWR because of its break up from radiation in the reactor core and its ineffectiveness as demonstrated in published test results. (“Development and Use of an In-Pile Loop for BWR Chemistry Studies,” MIT Nuclear Reactor Laboratory, Electric Power Research Institute, September 1993, pgs. 6-1 to 6-15.) However, it has been discovered that significant advantages can be obtained by shifting the focus of controlling vessel chemistry to reducing H2O2 prior to vessel water entering the reactor core and keeping N2H4 out of the reactor core.
 Turning to the figures, FIG. 2 shows a BWR system 200 including hydrazine injection according to a preferred embodiment of the present invention. In BWR system 200, feed water is provided to a feed water inlet 205 connected to feed water pumps 210 that supply feed water to reactor vessel 220, preferably through feed water heaters (not shown). Steam is produced from the feed water in reactor vessel 220 and supplied to a turbine 225 for production of electricity. After the steam flows through turbine 225, it is supplied to a condenser 230 where the steam is condensed to form condensate that is sent to condensate pumps 250, and preferably through feed water heaters (not shown), in preparation for returning condensate to feed water pump inlet 205. As is generally known and taught in the patents incorporated herein by reference, the steam produced from reactor vessel 220 contains a variety of gaseous substances in addition to steam. For example, the steam contains a substantial portion of hydrogen gas (H2) and oxygen gas (O2) and a small portion of radioactive gas that pass through condenser 230 and require removal. Accordingly, a steam jet air ejector 235 is provided for transporting these gases to an Advanced Off Gas (AOG) system 245 for further processing. AOG System 245 recombines the hydrogen and oxygen gases back into water (condensate) and sends the condensate to condensate pumps 250. AOG System 245 also renders the radioactive gases harmless.
 When BWR system 200 is operated without H2 injection, typically the steam exiting reactor vessel 220 contains a stoichiometric mixture of H2 and O2 since their source is the radiolytic decomposition of water. That is, water contains two hydrogen atoms for every one oxygen atom. Assuming H2 and O2 are the only decomposition products, two moles of H2 will exist in the steam for every one mole of O2. In reality, other decomposition products exist, but H2 and O2 are the primary products so at least an approximately stoichiometric mixture of H2 and O2 is provided in steam exiting reactor vessel 220. Nevertheless, condenser 230 typically suffers some air in-leakage and thus creates a more oxygen rich gas stream supplied to SJAE 235. The air in-leakage also enriches the steam from reactor vessel 220 with nitrogen since air is primarily composed from oxygen and nitrogen. Accordingly, AOG System 245 also separates nitrogen and excess oxygen from the reactor steam.
 When hydrogen injection is used to control IGSCC, excess hydrogen is typically injected to react with oxygen within reactor vessel 220. This creates an excess of hydrogen above the stoichiometric mix in reactor vessel 220 and in steam leaving reactor vessel 220. Excess hydrogen presents a detonation hazard. Also, one purpose of AOG System 245 is to form water (H2O) from H2 and O2. Thus, compensating oxygen must provided so that the H2 and O2 mixture becomes near stoichiometric and may be safely recombined into condensate in AOG System 245. FIG. 2 shows an oxygen injection system 270 that may be necessary to adjust the relative composition of hydrogen and oxygen by adding oxygen. Depending on the particular mechanisms used in AOG System 245, a desired relative composition for hydrogen and oxygen may be selected and controlled with oxygen injection system 270.
 For the present invention, it is predicted that the strategic addition of hydrazine into BWR system 200 will more effectively react with H2O2, creating less excess hydrogen in reactor vessel 220 and turbine 225 discharge gases. Thus, BWR System 200 according to a preferred embodiment of the present invention may require less air in-leakage or oxygen injection than conventional systems. Further, it is possible that oxygen addition by oxygen injection system 270 will not be required for BWR System 200. However, oxygen injection system 270 can be maintained to be conservative and, if needed, may utilize air addition (instead of pure oxygen addition) depending on the capabilities of AOG System 245 to handle non-condensable gases such as nitrogen from injected air. The preferred embodiment is inherently safer since the addition of oxygen by air in-leakage through condenser 230 and/or SJAE 235 is a passive addition and readily available during transient operation without complicated controls.
 Notably, a wide variety of equipment types and specifications may be provided for feed water pumps 210, reactor vessel 220, turbine 225, condenser 230, steam jet air ejector 235, AOG System 245, and oxygen injection system 270. Any suitable equipment known to those skilled in the art may be used for these listed components.
 To control IGSCC, a hydrogen injection system 260 is provided. Hydrogen injection system 260 and oxygen injection system 270 are optional aspects of BWR system 200 since it is conceivable that the circumstances of a particular BWR system will not require such equipment. BWR system 200 further includes a N2H4 injection system 280 for practicing the method according to a preferred embodiment of the present invention. Preferably, N2H4 injection system 280 provides N2H4 at an effective location to react with H2O2 in BWR system 200 and to reduce the amount of H2O2 to a desired amount in vessel water entering a reactor core (shown in FIG. 3) of reactor vessel 220. Preferably, N2H4 is injected in at least one feed water line upstream of feed water distributors (not shown) inside reactor vessel 220 such that N2H4 laden feed water is applied at a location wherein H2O2 may be reduced in vessel water entering the reactor core of reactor vessel 220.
 Notably, a variety of locations may be able to satisfy such criteria for N2H4 injection, even though FIG. 2 specifically shows N2H4 injection system 280 supplying N2H4 to a point upstream to feed water pumps 210. Other locations are conceivable in accordance with the features of the present invention described herein. For example, N2H4 is more preferably supplied such that the feed water distributers apply N2H4 laden feed water to liquid effluent returned from steam dryers/separators (shown in FIG. 3) to a mixing region of reactor vessel 220 in each occurrence. Most preferably, the feed water distributors indicated are feed water spargers as presently known to those skilled in the art and mixing region is mixing plenum inside reactor vessel 220 also as known to those skilled in the art.
 Turning now to FIG. 3, a cross-sectional view of reactor vessel 220 is shown. FIG. 3 particularly shows the distribution and flow of water within reactor vessel 220. Preferably, feed water enters reactor vessel 220 at one or more feed water inlets 305 and is approximately evenly distributed within a mixing plenum 350. Such distribution is preferably accomplished using feed water spargers (not shown). Following distribution within mixing plenum 350, vessel water flows downward and is either recirculated from a recirculation loop suction 315 to a recirculation pump and returned to inlet 320 or is pumped by jet pump 310 into a below core region 325. While recirculation is typically used in conventional reactor vessels, it is conceivable that a recirculation loop as shown in FIG. 3 may include a suction or inlet positioned differently than shown, or that no recirculation is provided. As discussed below, the extent of recirculation is important when considering the residence time of vessel water within reactor vessel 220 prior to entry into a reactor core 330.
 As also shown in FIG. 3, an outlet is provided within below core region 325 to send a portion of the vessel water to an optional reactor water cleanup unit (RWCU) 355 where selected undesirable components in the vessel water may be removed, for example, by using adsorptive resin or other systems. Vessel water thus cleaned is preferably returned to reactor vessel 220, typically through feed water 305. However, vessel water cleaned in RWCU 355 could alternatively be returned to a different part of reactor vessel 220 or BWR system 200. The outlet to RWCU 355 may be alternatively located at a different point on reactor vessel 220 or within BWR system 200 where feed water or steam dryer/separator liquid effluent may be cleaned up, although it is preferred that liquid effluent or water within reactor vessel 220 is cleaned up. FIG. 3 shows an additional outlet from recirculation loop suction 315 to RWCU 355 that may be operated in parallel with or in isolation from the outlet within below core region 325. That is, in the preferred embodiment shown in FIG. 3, vessel water may be removed from reactor vessel 220 either at below core region 325, at recirculation loop suction 315, or at both locations.
 Preferably, as shown in FIG. 3, a RWCU pump 370 is provided to facilitate supplying vessel water to RWCU 355 and delivering cleaned vessel water to its next location, preferably reactor vessel 220. RWCU pump 370 may, however, be located differently than shown and still provide the described function. FIG. 3 also shows that it is preferable to provide an optional ECP unit 375 to perform measurement of ECP outside of reactor vessel 220. Any method known to those skilled in the art may be used in ECP unit 375 to determine vessel ECP. For example, probes may be installed to determine ECP by analyzing the vessel water removed to ECP unit 375 or ECP unit 375 may be simply another sampling point to collect vessel water for analysis in a separate testing unit. Determination of ECP may be performed solely by chemical analysis of the water or by a combination of chemical analysis and estimation of the properties of vessel water. In addition, a separate sampling station 380 is provided for any further sampling needs.
 Vessel water flows from below core region 325 through reactor core 330 where it is boiled and heated to saturated steam. The saturated steam enters a steam separator 335, where water particles are removed, and then passes to a steam dryer 340 for further removal of non-gaseous water. The dried steam from steam dryer 340 passes through steam outlet 345 and on to turbine 225 as shown in FIG. 2, while the liquid effluent from steam separator 335 and steam dryer 340 flows down to mixing plenum 350. A typical water level 365 for mixing plenum 350 and a typical water level 360 for steam separator 335 are shown in FIG. 3.
 As is known to those skilled in the art, a wide variety of compounds are generated within reactor core 330 as vessel water and water impurities are exposed to radiation. H2 is one reducing species generated in reactor core 330 and O2 and H2O2 are two oxidizing species generated in reactor core 330. As an example of the distribution of species, prior analysis has shown the following concentrations in liquid effluent passing from steam separator 335 and steam dryer 340 to mixing plenum 350:
 This distribution was determined from a BWR system when not using hydrogen injection for IGSCC control. As indicated earlier, addition of H2 changes the vessel chemistry and accordingly would typically lower the concentration of O2 below the concentration indicated. Further analysis under the same conditions produced the following concentrations for vessel water entering jet pump 310 after combining liquid effluent in mixing plenum 350 with feed water having an O2 concentration of approximately 30 ppb:
 Still further analysis under the same conditions produced the following concentrations for vessel water in below core region 325:
 Given the much higher concentration of O2, compared to H2O2, one can readily understand the preoccupation in conventional methods for controlling IGSCC with H2 injection and catalytic enhancement to reduce the concentration of O2 through recombination with H2.
 Additionally, extensive testing and consideration of alternative chemical additives potentially useful in decreasing ECP (an indicator of the extent to which IGSCC will occur) has indicated that H2 injection continues to be the favored chemistry control method. Such testing included evaluation of N2H4, however, it also proved ineffective and undesirable. While recognized as an efficient oxygen scavenger, the testing nevertheless showed that N2H4 produced the highest level of carryover of radioactive nitrogen (N16) than any other additive tested as a potential candidate for reducing ECP, and thus IGSCC. (“Development and Use of an In-Pile Loop for BWR Chemistry Studies,” MIT Nuclear Reactor Laboratory, Electric Power Research Institute, September 1993, pgs. 6-1 to 6-15.)
 The focus in the testing was that N2H4 was targeted for reducing oxygen levels and was allowed to enter the reactor core. By contrast, the method according to a preferred embodiment of the present invention involves 1) selecting the amount of N2H4, the location of injection, and the residence time in reactor vessel 220 to target primarily the reduction in the level of H2O2 and 2) keeping N2H4 out of the reactor core. Using this approach, it can be seen that excellent results may be obtained in reducing IGSCC and improving monitoring of vessel chemistry without increasing N16 carryover into steam generated for power production. Achieving such beneficial results requires the realization that the reaction of N2H4 with H2O2 is predicted to occur at a rapid pace in a liquid phase to produce nitrogen (N2) and water. Because of the high thermal energy levels present in the BWR system 200 environment, rapid reaction of N2H4 with H2O2 is expected to occur with or without the presence of a catalyst.
 The combination of liquid N2H4 and liquid H2O2 has even been used as an important rocket propellant in the presence of ionic copper (Cu2+). However, the realization that the presence of Cu2+ catalyst may further enhance the reaction of N2H4 with H2O2 in a BWR has also been overlooked due to testing showing that the presence of Cu2+ interferes with the recombination of H2 and O2 to form water. Since the H2/O2 recombination is the primary reaction thought to be the key to reducing IGSCC, it is counterintuitive to realize that the presence of Cu2+ may nevertheless reduce IGSCC when H2O2 is targeted for reaction with N2H4.
 Turning now to FIG. 1, a diagram of the steps of a method according to a preferred embodiment of the present invention is shown. Method 100 is shown in FIG. 1 with basic steps 110, 120, 130, 140, and 150 as well as optional steps 105, 135, 155, 165, 175, and 185. Method 100 will first be discussed in terms of the basic steps and then further explanation will be provided regarding incorporation of optional steps into method 100. Steps 110, 120, 130, and 140 may be combined and summarized as the step of adding a sufficient amount of N2H4 at an effective location to react with H2O2 and to reduce an initial amount of H2O2 to a desired amount in vessel water entering a reactor core. However, there are several factors important in determining how much N2H4 to add and in selecting an effective location to accomplish the advantageous reduction of an initial amount of H2O2. Accordingly, method 100 shown in FIG. 1 breaks down the summarized step into at least four component parts.
 First, in step 110, a desired amount of H2O2 that is acceptable in vessel water entering reactor core 330 is selected. Preferably, the desired concentration of H2O2 in below core region 325 should be less than approximately 5 ppb. However, it is conceivable that other limits on the desired amount of H2O2 may be advisable. For example, instead of a concentration limit in parts per billion, it may be desirable to express the limitation on H2O2 amount as a mass flow rate, such as pounds per hour. Also, the limitation of 5 ppb H2O2 reflects a desire to reduce H2O2 to a de minimis level, but it is conceivable that some specified amount of H2O2 greater than 5 ppb may be acceptable in a particular BWR system. Accordingly, a de minimis amount for a particular BWR system may be greater than 5 ppb or it may be acceptable for vessel water entering reactor core 330 to contain more than a de minimis amount. Such selections may be made on a case-by-case basis for an individual reactor vessel 220, but generally, it is preferred to reduce H2O2 to less than approximately 5 ppb or an equivalent mass flow rate depending upon the flow rate of vessel water.
 Step 120 of method 100 involves selecting an effective location such that injected N2H4 will react with H2O2 to reduce the initial amount to the desired amount discussed above. Consideration must be given to the location inside reactor vessel 220 where favorable conditions for the reaction exist and where N2H4 can be added in BWR system 200 to reach the region for favorable reaction. As demonstrated by the data presented above, the most significant source for H2O2 in reactor vessel 220 is from the liquid effluent discharged from steam separator 335 and steam dryer 340. Accordingly, a preferable location for the reaction to occur is wherever injected N2H4 can be quickly mixed with steam dryer/separator liquid effluent flowing from steam separator 335 and steam dryer 340 to mixing plenum 350. Mixing the components quickly helps to prevent limitation of the reaction rate due to unavailability of the reactants when inadequate mixing occurs. It has been discovered that adequate mixing occurs when hydrazine is supplied through feed water inlet 305 as a mixture with feed water and distributed throughout mixing plenum 350 by feed water spargers (not shown).
 As presented above, the reaction of N2H4 with H2O2 has been used as rocket propellant in the presence of Cu2+ catalyst, thus, it can be estimated to occur almost instantaneously for the present purposes given the very low concentration of H2O2 and the complete mixing of N2H4 laden feed water with H2O2 in liquid effluent. Consideration must be given however to several competing factors. First, the temperature and radiation exposure under which the reaction occurs will both influence reaction rate. Second, depending on the reaction rate of N2H4 with O2 in the feed water that delivers the N2H4 to mixing plenum 350, part of the N2H4 may be prematurely consumed. As is known to those skilled in the art, the rate of a reaction is typically influenced by temperature, pressure, concentration of the reactants and the products, pH, catalysts, and other conditions.
 Given the typical operating conditions of BWR system 200, as described in the patents incorporated by reference above, and a typically low oxygen concentration in feed water of approximately 30 ppb, the reaction rate of N2H4 with O2 can be assumed to be relatively slow. Further, previous testing has shown the ineffectiveness in a BWR of N2H4 as an O2 reducer, thus, for a residence time of 90 seconds or less in feed water prior to encountering the H2O2 reaction region, it can be assumed that the depletion of N2H4 by reacting with O2 is minimal. A detailed evaluation of this assumption is provided in the examples below. Nevertheless, it is conceivable that conditions may be encountered where additional N2H4 must be added to account for depletion of N2H4 by the reaction with O2 such that a sufficient amount of N2H4 is delivered to the region where the primary reaction with H2O2 will occur. Such a calculation of additional needed N2H4 is within the knowledge of those skilled in the art given the disclosure provided herein and the knowledge available concerning the N2H4/O2 reaction. For some BWR systems, it may even be desirable to add enough extra N2H4 to achieve some limited consumption of O2 with N2H4 after virtually all of the H2O2 has been consumed in the H2O2 reaction region. The N2H4 used for O2 scavenging may even be injected at a different location than that used for H2O2 scavenging, for example, one alternate location is the suction to a recirculation pump.
 Accordingly, selection of the injection location in step 120 of method 100 may be considered to be closely intertwined with step 130 of determining the amount of N2H4 to add. Once given the desired amount of H2O2 for vessel water entering reactor core 330 and the N2H4 injection location, other factors must be considered to select the amount of N2H4 to inject. First, consideration should be given to the amount of H2O2 present in the reaction region. For example, the data presented above indicated a typical concentration of 500 ppb for liquid effluent in mixing plenum 350 prior to mixing with feed water from feed water inlet 305. Obviously, the actual amount of H2O2 present will depend upon the design and operating conditions of a particular BWR system and may be determined through vessel water analysis and/or empirical estimation. Knowing the amount of H2O2 present in the reaction region, the target for the reduced amount of H2O2, and any needed excess to counteract reaction with O2 in the feed water should provide sufficient information to determine a sufficient amount of N2H4 to inject. Nevertheless, additional amounts of N2H4 may be desirable depending upon the vessel chemistry scenario selected for reactor vessel 220.
 As stated above, it is preferable to reduce the amount of H2O2 to less than 5 ppb, however, there may be circumstances where a higher or lower limitation is desired. Also, it may be desirable to additionally react N2H4 with O2 in the reaction region to reduce an initial amount of O2 to a desired amount in vessel water entering the reactor core. As stated earlier, the reaction rate of N2H4 and O2 in feed water can be considered relatively slow. However, the concentration of O2 and other conditions, such as temperature and pressure, may be sufficiently higher in the vessel water to produce an increased reaction rate that would not be considered minimal. For example, an O2 concentration of 175 to 225 ppb is typical in vessel water. Given the possibility of decreasing the amount of O2 along with the amount of H2O2, additional N2H4 may be injected to accomplish the reduction.
 Next, step 140 of method 100 involves injecting a sufficient amount of N2H4 to achieve the effects selected in the steps above. In step 150, a determination is made whether sufficient residence time was provided to consume all but a tolerable amount of the N2H4 prior to the treated vessel water entering reactor core 330. If a determination is made that the tolerance of BWR system 200 to byproducts that result from the presence of N2H4 in reactor core 330 has been exceeded, then steps 120 and 130 should be reconsidered to meet the needed tolerance level. Preferably, for most BWR systems, consuming all but a tolerable amount of the N2H4 will require consuming substantially all of the N2H4. More preferably, consuming substantially all of the N2H4 should yield less than approximately 5 ppb N2H4 in vessel water entering reactor core 330.
 Nevertheless, it is conceivable that BWR system 200 may be more or less tolerant of N2H4 such that a higher or lower limit may be met while still being able to consider the decomposition of N2H4 to produce a de minimis amount of N16 in steam supplied to turbine 225. Thus, yet another vessel chemistry scenario provides reduction of H2O2 to a desired amount, and reduction of O2 to a desired amount and leaving somewhat more than 5 ppb N2H4 in vessel water entering reactor core 330. If the inquiry of step 150 is satisfied, then the basic steps of method 100 are considered complete.
 The optional steps of method 100 shown in FIG. 1 may be incorporated into the basic method described above depending upon the need for and desirability of such additional steps for a given BWR system. In optional step 105, a determination may be made as to the initial amount of H2O2 in liquid effluent returned from steam separator 335 and steam dryer 340 for combination with the feed water in mixing plenum 350. This information may then be used in optional step 135 to select the sufficient amount of N2H4 at least partially based upon the initial amount of H2O2 in the liquid effluent. In the conventional methods for reducing IGSCC discussed above, no significant consideration has been given to targeting the H2O2 in steam dryer/separator liquid effluent for rapid reaction with N2H4. Thus, optional step 105 presents another shift from the practice in conventional methods and helps enable some of the advantages discussed herein.
FIG. 1 also shows optional step 145 of enhancing the reaction of N2H4 with H2O2 by using a catalyst. It is conceivable that a variety of catalysts (such as those including elements from the noble metal group) could potentially enhance the reaction. However, Cu2+ is known to catalyze the N2H4/H2O2 reaction when the reactants are used as rocket propellant. Further, the vessel water of a BWR system may contain a catalytically effective amount of minerals such as Cu2+ and not require the addition of a separate catalyst. It is estimated that between 5 to 15 ppb Cu2+ is a catalytically effective amount of one mineral that can further catalyze the N2H4/H2O2 reaction.
 One of the advantages of a preferred embodiment of the present invention is that it may be used in combination with conventional methods for reducing IGSCC, such as use of a noble metal catalyst, for example, platinum and/or rhodium, to promote combination of H2 and O2 to form H2O. The preferred embodiment is predicted to be compatible with the conventional method of promoting H2/O2 recombination by adding excess H2. Both of these conventional methods are disclosed in the patents herein incorporated by reference above.
 Aside from reducing IGSCC when controlling vessel chemistry of BWR system 200 as described above, method 100 may also be used to improve the cost effectiveness of monitoring vessel chemistry. Accordingly, optional step 155 includes collecting a sample of vessel water upstream of the reactor core and optional step 165 includes obtaining a complete assessment of vessel chemistry by analyzing the sample only for the presence of components other than H2O2. This sampling may be accomplished by drawing a sample of vessel water at sample station 380 shown in FIG. 3 or another sample station and analyzing for N2H4 fragments and ECP as discussed below. Alternatively, the sampling may be accomplished by providing ECP unit 375 stationed outside reactor vessel 220 where it can be readily accessed for data collection and maintenance needs. Further, still other sampling and analysis methodologies as known to those skilled in the art may be used.
 The two additional steps (155 and 165) are enabled by the other steps of method 100 because H2O2 may be targeted for removal prior to vessel water entering the reactor core. One of the problems in monitoring vessel chemistry is that H2O2 is extremely difficult to measure in an BWR vessel because thermal decomposition and decomposition induced by contact with the walls of sample lines combine to produce hard-to-measure concentrations of this species in a BWR system 200. Accordingly, the amount of H2O2 in mixing plenum 350 can be assessed and estimated as close as possible and then reacted with a known amount of N2H4 according to method 100. Since the amount of O2 is also known, testing below core region 325 for the presence of O2 will indicate whether the correct amount of N2H4 was added for the estimated amount of H2O2. If too little H2O2 was estimated, then the excess N2H4 will react with and reduce the amount of O2, producing an O2 amount in below core region 325 that is less than the O2 in mixing plenum 350. Accordingly then, steps 155 and 165 may be used to ensure that the components in the vessel water are correctly assessed or may additionally be used to ensure that the presence of H2O2 in mixing plenum 350 is correctly assessed.
 Optional steps 175 and 185 in combination with the basic steps of method 100 provide yet another advantage in controlling vessel chemistry of BWR system 200. In optional step 175, vessel water upstream of reactor core 330 is examined to assess the type and amount of N2H4 fragments, such as N2, ammonium hydroxide (from ammonia), and unreacted N2H4, and the information obtained is used in optional step 185 of calculating ECP from the type and amount of N2H4 fragments. Accordingly then, steps 175 and 185 enable using N2H4 injection as set forth in method 100 as a tool to determine the ECP within reactor vessel 220. The approach involves first establishing a baseline of vessel chemistry in below core region 325. The baseline should provide an indication of ECP in relation to the chemical components of vessel water in below core region 325. Next, a new baseline of vessel chemistry in below core region 325 is established while using N2H4 injection. Preferably, the process could be partially baselined by testing N2H4/H2O2 reactions offline under laboratory conditions. The new baseline should also provide an indication of ECP in relation to the chemical components, in particular N2H4 fragments.
 In keeping with the vessel chemistry scenarios described above, different injection rates of N2H4 will yield different amount and/or types of components. By using the first baseline and the new baseline, ECP may be calculated or measured based on the amount and types of components present in below core region 325. For example, if no N2H4 or ammonium hydroxide fragments are found and H2O2 is totally consumed, then ECP may be determined by considering the amount of O2 present in the offline sample. If N2H4 fragments exist, then the ratio of fragments will inform of the H2, O2, and H2O2 distributions. Such distributions can then be used to calculate ECP.
 An example of one way in which the baselining data may be presented is shown in the graph of FIG. 4 plotting N2H4 concentration in feed water against ECP. Notably, for this example, up to about 1500 ppb N2H4 substantially all of the N2H4 is consumed primarily by reaction with H2O2, but with little impact on O2 concentration. The concentration of N2H4 in feed water on the x-axis will determine the concentration of residual H2O2 that remains in vessel water after all the N2H4 is consumed. As the concentration N2H4 in feed water rises up to 1500 ppb, the concentration of residual H2O2 decreases to zero at the point where enough N2H4 is present to consume all of the H2O2. At the point where all H2O2 is consumed (approximately 1500 ppb N2H4) the actual ECP inside reactor vessel 220 is the same as the ECP determined by external monitoring using one of the methods described above. If less than 1500 ppb N2H4 is provided in the feed water, then residual H2O2 will exist in vessel water and the in-vessel ECP will be greater than the ECP indicated by external monitoring. If more than 1500 ppb N2H4 is provided in the feed water, then at least a portion of the O2 in vessel water will be consumed, further decreasing ECP. Noticeably, however, in-vessel and external ECP are the same once all the H2O2 is consumed as is the case for N2H4 concentrations above 1500 ppb in the example described in FIG. 4.
FIG. 4 thus shows the difference between in-vessel and external ECP in a qualitative fashion as a function of N2H4 concentration in feed water. Such a graph may be produced for any BWR after collecting the data from baselining as described above. Once developed, a graph such as FIG. 4 may be used to estimate in-vessel ECP based only on the concentration of N2H4 in feed water. The estimate may be checked by external monitoring of ECP to verify that the predicted external ECP is obtained. If the predicted and actual external ECP match, then the in-vessel ECP is confirmed. If the predicted and actual external ECP do not match, then some parameter on which FIG. 4 is based, such as the concentration of O2 or H2O2 in vessel water prior to reaction with N2H4 may have changed and a new graph such as FIG. 4 may be required.
 In keeping with the above principles described for the preferred embodiments of the present invention, examples of how such principles are used to practice the invention are set forth below.
 For normal hydrogen water chemistry (injection of hydrogen to control IGSCC) to achieve protection, current technology requires significant excess hydrogen. For example, 27 ppb of excess hydrogen is needed to stoichiometrically react with 216 ppb of oxygen according to the reaction 2H2+O2=2H2O and Table 3. However, typical field experience shows that required hydrogen levels for below core region 325 range between 15 50 ppb to 250 ppb. In other words, about 2 to 9 times the stoichiometric concentration of hydrogen is needed for protection. Additionally, this excess hydrogen encourages radioactive ammonia formation, which can raise steam line radioactive dose rates by a factor of 5.
 For hydrogen addition with noble metal catalysis, field experience shows that protection can be achieved with hydrogen additions between 0.9 to 2 times stoichiometric values. The reduced hydrogen addition requirement significantly reduces radiation dose rate in most BWRs. However, the dose increase caused by hydrogen injection may still be significant if copper ions are present in the water. For example, dose rate increases may be as low as 0% with stoichiometric hydrogen additions, but dose rate may double if 2 times the stoichiometric amount of hydrogen is injected, and 5 to 15 ppb copper ions are present in vessel water.
 For hydrazine chemistry (injection of N2H4 to control IGSCC) as described herein, N2H4 may be injected to react with H2O2 and, possibly, O2 to create a favorable ECP in the reactor vessel and lower crack growth rates. If all of the added N2H4 is consumed prior to the vessel water entering the reactor core, the hydrogen atoms in N2H4 are not available to form radioactive ammonia and increase radiation dose rate. Copper ion (if present) is beneficial in reducing dose rate, rather than detrimental as with hydrogen/noble metal water chemistry, since copper ion tends to catalyze the N2H4 reaction to proceed more rapidly. Rapid consumption of N2H4 helps to further ensure that intolerable amounts of N2H4 are not allowed into the reactor core. Hydrazine chemistry thus reduces the excess hydrogen available to form radioactive ammonia, thereby keeping radioactive doses low (e.g. projected between 0% and 5% increase). Hydrazine water chemistry is also predicted to work with noble metals chemistry, yielding similar ECP benefits but with low radioactive ammonia formation.
 The current technology for both hydrogen water chemistry and hydrogen/noble metals water chemistry require a separate, significant oxygen source to recombine excess hydrogen that is not recombined in the reactor vessel. This technology requires sophisticated control systems to avoid accumulations of hydrogen which could cause detonations. It also requires the purchase of oxygen, which increases the cost of operation.
 The hydrazine/hydrogen peroxide reaction is predicted to be very nearly complete in BWR reactor vessel 200. The excess hydrogen that is formed will be supplied primarily from steam dryer/separator liquid effluent and some incomplete hydrazine/hydrogen peroxide reaction. This excess hydrogen volume is predicted to be much smaller than either of the current technologies, and therefore can be totally recombined with oxygen available from condenser air in-leakage before being sent to AOG System 245.
 For example, if 1500 ppb hydrazine is added to feed water (flow rate=2.9×106 kilograms/hour (kg/hr) (6.4×106 pounds/hour (lbs/hr))) to create a pre-reaction concentration of 237 ppb hydrazine in the mixing plenum, then 500 ppb hydrogen peroxide can be consumed. This represents a hydrazine addition rate 4.47 kg/hr (9.85 lbs/hr). The equivalent hydrogen concentration contained within the hydrazine is about 200 ppb at feed water flow rates. If all this hydrogen remained uncombined (an unexpected occurrence), the oxygen available from a typical condenser air in-leakage rate of 0.42 cubic meters/minute (cmm) (15 cubic feet/minute (cfm)), would consume the hydrogen with approximately at 15% oxygen volume excess. Although it is recommended to provide a port for oxygen (or air) addition after the condenser, it is anticipated that additional oxygen will not be regularly needed for hydrazine water chemistry. Since oxygen addition is passively accomplished with air in-leakage, the control system is much simpler, and the cost of controls is reduced.
 The consumption rate of hydrazine for a BWR system is significant but manageable and can be achieved using portable equipment at a modest rental fee. Although the operating costs are estimated to be up to 5 times more than a hydrogen injection system, the significant savings is realized in capital expenditures. It is estimated that hydrazine capital equipment costs are approximately 30 to 70 times less than a hydrogen injection system. The primary reasons are simpler control equipment and smaller equipment footprint. A hydrazine addition system may be more cost effective for up to 20 years. However, to achieve this favorable balance, both ECP field performance and reactor water cleanup resin usage (to address hydrazine impurities) of the hydrazine addition system must be verified.
 For a BWR reactor vessel, vessel water can enter the below core region rapidly when it is “driven” directly through the jet pumps. When this flow path is taken, there is approximately 10 to 15 seconds (sec) for a reaction to take place before excess N2H4 potentially enters the reactor core. Hydrazine can adequately react with H2O2 during this time, but will only partially react with oxygen which requires about 30 sec at 200° C. to 230° C. (400° F. to 450° F.). For this reason, H2O2 is the primary target. Since H2O2 is considered the more aggressive oxidizer, and a significant source of oxygen to the below core region (e.g. supplies approximately 40% to 50% of the O2 when it breaks down from H2O2 to water and oxygen), eliminating hydrogen peroxide in the mixing plenum will have a significant effect on improving ECP in the downcomer, recirculation, and below core regions of a reactor vessel.
 Hydrazine may also react with O2 in the feed stream (normally feed water 305 of FIG. 3). Depending on plant configurations, residence times will vary significantly but nominally between 30 to 50 sec. Since 1) oxygen concentrations are typically low in feed water streams (nominally 30 ppb) and 2) temperatures are below optimum hydrazine reaction temperature of hydrazine at about 200° C. (400° F.) for most of the piping run, consumption of hydrazine before entering the vessel mixing plenum is considered typically low.
 The N2H4 injection rate is targeted such that 1) most N2H4 remains unreacted until it reaches the mixing plenum, 2) adequate N2H4 may be provided to react with H2O2 in the liquid effluent from steam separators and steam dryers, and 3) a small excess may be supplied to provide limited O2 reduction. Since the N2H4/H2O2 reaction is judged to be near instantaneous, it is estimated that 10 to 15 sec is adequate for near complete consumption, but may be limited by mechanical mixing capability. Hydrazine begins to break down from thermal exposure at about 200° C. (400° F.) and the below reactor core residence time of 10 to 15 sec is less than the about 30 sec needed for a complete N2H4/O2 reaction at 200° C. to 230° C. (400° F. to 450° F.). Thus, it is estimated that only 33% of the available O2 will react with N2H4 before entering the reactor core. Therefore, it is necessary to keep targeted O2 amounts small, to avoid carryover of N2H4 to the core with consequential undesirable decomposition within the reactor core.
 In reference to the method shown in FIG. 1, the following example explains one method for determining the proper amount of hydrazine (and catalyst) needed to scavenge hydrogen peroxide and oxygen in a BWR. One goal of the method is to scavenge these oxidizers to provide IGSCC protection without a significant increase in main steam line doses.
 1 Determine Amount of H2O2 in Liquid Effluent (Step 105):
 Prior art has shown that water discharge from moisture dryers and separators (335 and 340), has the following typical approximate concentrations: H2=20 ppb; O2=175 ppb; H2O2=500 ppb.
 2. Select Desired Amount of Residual H2O2 to Remain (Step 110):
 It is most preferable to remove 100% of the H2O2 if possible since it is a significant liquid oxidant. Therefore the first estimate should assume an ideal stoiciometric mix of N2H4 to consume all H2O2 in a complete reaction. If the reaction is not nearly 100% complete, the decision of an acceptable H2O2 residual must be made. The quantity of acceptable residual depends on whether: a) acceptable ECPs are achieved (e.g. ECP=−230 mev or lower); b) constant or small increases in main steam line dose rates are achieved; and c) the auto breakdown rate of H2O2 to water and O2 (a second parallel reaction) is confirmed significant. The N2H4 rapidly consumes O2 (even at low concentrations), and significant oxidant can be removed by this second parallel reaction.
 If an acceptable ECP is not achieved through this process, indicating that both N2H4/H2O2 and H2O2 auto breakdown reactions are slower than anticipated, a catalyst must be added and/or increased to make the N2H4—H2O2 reaction more effective.
 3. Select an Effective Injection Location (Step 120):
 The N2H4 must be injected in a location such that it remains stable until it encounters H2O2. One example of an effective injection location is the feedwater (FW) system (FIG. 2, 280 into 210). The FW injection point is generally effective because:
 a. FW temperatures are lower than reactor vessel temperatures (300 F to 375 F) so that the N2H4 is not as actively scavenging residual O2 in the FW system. This can be seen by the following equation which estimates the hydrozine-oxygen reaction kinetics at a given temperature T (° K):
 As is evident by the foregoing equation, for the temperatures in the FW line, the reaction rate is approximately 10,000 times slower in the FW line than it is in the vessel. This slower reaction rate helps maintain protective films on carbon steel pipe in the FW system where it is required to be at 30 ppb or higher and preserves N2H4 for the target point (e.g. moisture separator and dryer effluent at the FW nozzles).
 b. There is no H2O2 in the feedwater stream to consume (which further preserves N2H4 until needed).
 c. Vessel temperatures are typically about 527° F. Studies have shown that N2H4 is stable and active in this high temperature region, and ready to consume H2O2, where concentrations are highest and the initial reaction is vigorous.
 4. Determine the Amount of N2H4 to Inject (Step 130):
 The amount of N2H4 to inject is determined by molar ratio from known reactions:
 and conversion of weight concentrations into molar concentrations:
 The N2H4 required equals that molar quantity needed to consume both O2 (regularly performed for fossil boilers) and the H2O2 (that substance which is not present in fossil boilers but is present in nuclear boilers). In other words, we need: 5.47 lbmoles N2H4 per billion lbs mix to neutralize O2; 7.4 lbmoles N2H4 (e.g. 14.7/2 ) per 1 billion lbs mix to neutralize H2O2 and the N2H4 needed to achieve stoiciometric balance (e.g. 12.82 ibmoles N2H4, or 410 ppb N2H4). Flow weighting factors may be applied to adjust for differences in FW flow rates and internal core flow rates which are approximately four times higher.
 5. If Possible Enhance the Reaction with a Catalyst (Step 145):
 Although the N2H4/H2O2 reaction is thermodynamically very favorable, the dilute concentrations (ppb range) significantly slow down reaction times. Since the allowable reaction time is short (approximately 10 to 15 seconds), the use of catalysts to accelerate the reactions is preferable. For some reactors, catalysts may already exist. For example, in a typical plant that uses an admiralty condenser, 6 ppb Cu+2 (10E-07 molar) or more may be present in its reactor vessel. This catalyst may significantly catalyze the desired reaction at BWR temperatures. The consumption rate for N2H4 can be described as a first order equation dependent on Cu+2 concentration and H2O2 concentration. When adjusted for temperature of the BWR (by Arrhenius method), the reaction rate may reach approximately 500 times the reaction rate of that at near room temperatures, e.g.:
 Since 2 moles of H2O2 are consumed per mole of N2H4 then:
 Therefore, for a 15 sec period, and 6 ppb Cu+2 concentration in the reactor, typical H2O2 could be crudely approximated by:
 At this rate, only about 20% of the H2O2 would be consumed and this reaction alone would result in carryover of residual N2H4 to the core. Ordinarily, this would be unacceptable. However, with the parallel breakdown reaction of H2O2 to water and O2, and the subsequent rapid consumption of O2 by remaining N2H4, as indicated by the equations shown herein, it is anticipated that this pairing of reactions will result in only minute amounts of H2O2 and N2H4 reaching the core.
 Reaction rates may be additionally improved if the concentration of the catalyst is increased. These improvements may result from the presence of platinum and rhodium from other catalytic ventures, or from a specialty equivalent organic catalyst supplied by the hydrazine vendors. Additionally, the annulus and recirculation pipe region is exposed to a relatively high gamma field which can provide additional activation energy to accelerate the reactions, as it does for the conventional H2/O2 reaction to form water in this region.
 Applicant's studies indicate that the consumption rate of O2 with N2H4 can be expressed by O2 half life. At 500° F., the half life of O2 with N2H4 is approximately 0.06 seconds. Therefore, there are approximately 250 half lives in the 15 seconds of allowable reaction time, and virtually all O2 (and N2H4 used to consume it) will be consumed before reaching the core.
 6. Inject the Prescribed N2H4 and Measure Results (Step 130, and Steps 150 Through 185):
 Based on steps 1-5 above, the ideal N2H4 concentration may be determined. To ensure that proper vessel dynamics are established, the following iterative procedure should be considered:
 a. Target initial injection at 10% of this ideal concentration and subsequently increase N2H4 by approximately 10% increments (or any other increments) to 100% of the amount determined through steps 1-5 to ensure minimum system impact.
 b. Monitor main steam line radiation dose rates during this time period, to ensure steady values. If the reaction is 100% effective, no dose increase will result. Dose rates will increase if the reaction is not 100% effective.
 c. Monitor advanced offgas system (AOG) offgas for increases in N2 concentration. If the reaction is nearly 100% effective, the N2 formerly contained in the N2H4 will flow through the reactor and not form soluble nitrates. A mass balance of gaseous N2 from N2H4 recombination and air in-leakage can then be used to verify success.
 d. Monitor Reactor Water Cleanup for N2H4 fragments (primarily soluable nitrates). The lack of an increase in soluble nitrates indicates the consumption reaction is effective.
 e. If available, measure ECP. IGSCC protection is achieved if ECP is less than −230 mev.
 While the invention has been particularly shown and described with reference to preferred embodiments thereof, it will be understood by those skilled in the art that various changes in form and details may be made therein without departing from the spirit and scope of the invention. Accordingly, unless otherwise specified, any dimensions of the apparatus indicated in the drawings or herein are given as an example of possible dimensions and not as a limitation. Similarly, unless otherwise specified, any sequence of steps of the method indicated in the drawings or herein are given as an example of a possible sequence and not as a limitation.