Water Chemistry Experience of Nuclear Power Plants in Japan

Ishigure, Kenkichi; Abe, Kenji; Nakajima, Nobuo; Nagao, Hiroyuki; Uchida, Shunsuke

doi:10.1080/18811248.1989.9734280

Cited by 14 publications

(6 citation statements)

References 7 publications

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“…Accordingly, their participation in determining the ECP is readily incorporated by redefining the concentrations of H 2 , O 2 , and H 2 O 2 , as noted above. The most extensive work on modeling the coolant chemistry of fission reactors, at least in terms of the numbers of operating reactors modeled, appears to be that reported by Macdonald et al in the USA [216][217][218][219][220][221][222][223][224][225][226][227][228][229][230][231][232][233][234], Ibe and Ishigure in Japan [74,206,208,271], and by Yeh and co-workers in Taiwan [281][282][283][284][285][286][287][288][289], with the former dealing with fourteen operating BWRs and PWRs worldwide and the latter having modeled several BWRs, including Advanced BWRs, and a proposed Super Critical Water Reactor (SCWR) [288]. These models are now undergoing major refurbishment by inclusion of advanced submodels for calculating the ECP and damage due to stress corrosion cracking.…”

Section: Nomentioning

confidence: 99%

A Critical Review of Radiolysis Issues in Water-Cooled Fission and Fusion Reactors: Part I, Assessment of Radiolysis Models

Macdonald

Engelhardt

Petrov

2022

CMD

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A critical review is presented on modeling of the radiolysis of the coolant water in nuclear power reactors with emphasis on ITER. The review is presented in two parts: In Part I, we assess previous work in terms of compliance with important chemical principles and conclude that no model proposed to date is completely satisfactory, in this regard. Thus, some reactions that have been proposed in various radiolysis models are not elementary in nature and can be decomposed into two or more elementary reactions, some of which are already included in the models. These reactions must be removed in formulating a viable model. Furthermore, elementary reactions between species of like charge are also commonly included, but they can be discounted upon the basis of Coulombic repulsion under the prevailing conditions (T < 350 °C) and must also be removed. Likewise, it is concluded that the current state of knowledge with respect to radiolytic yields (i.e., G-values) is also unsatisfactory. More work is required to ensure that the yields used in radiolysis models are truly “primary” yields corresponding to a time scale of nanoseconds or less. This is necessary to ensure that the impact of the reactions that occur outside of the spurs (ionizing particle tracks in the medium) are not counted twice. In Part II, the authors review the use of the radiolysis models coupled with electrochemical models to predict the water chemistry, corrosion potential, crack growth rate in Type 304 SS, and accumulated damage in the coolant circuits of boiling water reactors, pressurized water reactors, and the test fusion reactor, ITER. Based on experience with fission reactors, the emphasis should be placed on the control of the electrochemical corrosion potential because it is the parameter that best describes the state of corrosion in coolant circuits.

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Section: Nomentioning

confidence: 99%

A Critical Review of Radiolysis Issues in Water-Cooled Fission and Fusion Reactors: Part I, Assessment of Radiolysis Models

Macdonald

Engelhardt

Petrov

2022

CMD

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“…Balanced coolant water chemistry is indispensable for the optimum performance of nuclear power plants. The role and effect of constituent ions, mainly lithium (Li) and boron (B), in PWR water has been previously studied in detail by numerous researchers [19][20][21][22][23]. The PWR water chemistry greatly deviates from the optimum chemistry during the plant startup and shutdown, resulting in the release of corrosion products.…”

Section: Introductionmentioning

confidence: 99%

Effect of thermal aging on corrosion behavior of duplex stainless steels

et al. 2022

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Despite their exceptional mechanical and corrosion properties, duplex stainless steels (DSS) have not found widespread use in high-temperature applications due to concerns over thermal aging and embrittlement at elevated operational temperatures (> 300 °C). The present study investigated the effect of thermal aging time on the electrochemical properties of lean and standard grade DSS that are exposed to a range of pressurized water reactors containing LiOH and H3BO3. The results indicated that the electrolyte chemistry plays a significant role in the corrosion behavior of the DSS alloys. Corrosion resistance decreased with thermal aging time for all DSS alloys; however, standard grade DSS (2205 and 2209-w) alloys showed better corrosion resistance than lean grades (2003, 2101, 2101-w). The presence of dissolved oxygen in the electrolytes resulted in a significant increase in corrosion rate for the DSS alloys, but it did not affect the general trend of corrosion rates with aging time. All DSS alloys became vulnerable to pitting corrosion due to chloride addition, but the pitting resistance decreased with increasing thermal aging time. Increased boron B content resulted in degradation of corrosion resistance of the DSS alloys, while minor changes in pH did not show a significant change in corrosion resistance. Mechanical and metallurgical characterization coupled with electrochemical characterization of the DSS alloys gave a comprehensive insight into the effects of thermal aging on the electrochemical response of the DSS. Graphical abstract

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“…Boron, as boric acid, is being added in the primary water coolant system of Pressurized Water Reactor (PWR) as a fine neutron moderator [1][2][3][4]. In addition to that, boric acid has been used for moderating the coolant water in interim spent fuel storage at accident affected Fukushima units.…”

Section: Introductionmentioning

confidence: 99%

Boric Acid Radiolysis in Primary Coolant Water of PWR at Temperature of 250oC

Sunaryo

2017

Jurnal Pengembangan Energi Nuklir

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BORIC ACID RADIOLYSIS IN PRIMARY COOLANT WATER OF PWR AT TEMPERATURE OF 250o C. The existence of oxygen in the primary coolant system of PWR could lead to corrosion, hence it is very important to suppress the oxygen concentration in the system. Therefore, study of the effect of boric acid addition into the primary coolant water system of PWR to suppress oxygen concentration resulted from gamma-ray radiation is essential to be performed. The aim of this research is to understand reaction mechanism at temperature of 250 0 C and the effect of boric acid adding toward oxygen concentration in the PWR primary coolant water. Methodology used is simulation using Facsimile software. Input for the software namely radiolysis reaction mechanism for pure water, G value from radiolysis product, dose rate of 1 and 10 4 Gy/s, aeration and deaeration system, and specific reaction of boric acid with hydroxyl radical and hydrated electron at temperature 25 0 C and 300 0 C. The output are in the form of irradiation time vs oxygen concentration time series. The results show that the oxygen production increase significantly with the irradiation time and reach the saturated concentration at 10 7 s. Based on the plot of oxygen's concentration at 10 7 s vs boric acid, several results are as following: oxygen concentration significantly suppressed by boric acid addition and gives the exponential decreasement, the higher dose rate gives the higher concentration of oxygen, the aeration system gives no effect on suppressing oxygen concentration at boric acid addition up to 0.1M. ABSTRAK RADIOLISIS ASAM BORAT DI AIR PENDINGIN PRIMER PWR PADA TEMPERATUR 250o C. Adanya oksigen di dalam sistem pendingin primer PWR dapat menyebabkan korosi sehingga sangat penting untuk menekan konsentrasi oksigen dalam sistem tersebut. Oleh karena itu, studi pengaruh penambahan asam borat ke dalam air pendingin primer dari PWR untuk menekan konsentrasi oksigen yang dihasilkan akibat radiasi sinar-gamma penting untuk dilakukan. Tujuan penelitian adalah untuk memahami mekanisme reaksi hingga temperatur 250 0 C dan pengaruh penambahan asam borat terhadap konsentrasi oksigen di dalam sistem pendingin primer PWR. Metodologi yang digunakan adalah simulasi menggunakan perangkat lunak Facsimile. Input yang digunakan adalah mekanisme reaksi radiolisis untuk air murni, nilai-G dari produk radiolisis, laju dosis 1 dan 10 4 Gy/s, sistem aerasi dan deaerasi, dan reaksi spesifik dari asam borat dengan radikal hidroksil dan electron terhidrasi, pada temperatur 25 o C dan 300 o C. Keluarannya berupa data runtun waktu iradiasi vs konsentrasi oksigen. Hasil simulasi menunjukkan bahwa produksi oksigen naik secara signifikan dengan lamanya waktu iradiasi dan mencapai kondisi tunak pada t=10 7 s. Berbasis hasil plot antara konsentrasi oksigen pada t=10 7 s vs konsentrasi asam borat, memberikan hasil sebagai berikut: konsentrasi oksigen ditekan secara signifikan oleh adanya asam borat dan memberikan penurunan secara eksponensial, pengaruh laju dosis menunjukkan bahwa semakin tinggi l...

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Water Chemistry Experience of Nuclear Power Plants in Japan

Cited by 14 publications

References 7 publications

A Critical Review of Radiolysis Issues in Water-Cooled Fission and Fusion Reactors: Part I, Assessment of Radiolysis Models

A Critical Review of Radiolysis Issues in Water-Cooled Fission and Fusion Reactors: Part I, Assessment of Radiolysis Models

Effect of thermal aging on corrosion behavior of duplex stainless steels

Boric Acid Radiolysis in Primary Coolant Water of PWR at Temperature of 250oC

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