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JAEA Reports

Hydrochemical investigation at the Mizunami Underground Research Laboratory; Compilation of groundwater chemistry data in the Mizunami group and the Toki granite (fiscal year 2016)

Watanabe, Yusuke; Hayashida, Kazuki; Kato, Toshihiro; Kubota, Mitsuru; Aosai, Daisuke*; Kumamoto, Yoshiharu*; Iwatsuki, Teruki

JAEA-Data/Code 2018-002, 108 Pages, 2018/03

JAEA-Data-Code-2018-002.pdf:6.53MB

Japan Atomic Energy Agency has been investigating groundwater chemistry to understand the effect of excavation and maintenance of underground facilities as part of the Mizunami Underground Research Laboratory (MIU) Project in Mizunami, Gifu, Japan. In this report, we compiled data of groundwater chemistry and microbiology obtained at the MIU in the fiscal year 2016 and 2014 to 2016, respectively. In terms of ensuring traceability of data, basic information (e.g. sampling location, sampling time, sampling method and analytical method) and methodology for quality control are described.

Journal Articles

Advanced water chemistry control based on parameters determined with plant simulation models

Uchida, Shunsuke; Hanawa, Satoshi; Lister, D. H.*

Power Plant Chemistry, 17(6), p.328 - 339, 2015/12

In nuclear power plants, radiation makes the relationship between structural materials and water chemistry much more complex than that in fossil fueled power plants. It is difficult to maintain safer and more reliable plant operation by controlling water chemistry based on only a restricted number of measured data. It is often required to control water chemistry with suitable assistance from computer models, which can extrapolate measured water chemistry parameters to those at the required locations and predict future trends of the interactions between structural materials and water chemistry. In the paper, water chemistry control based on parameters determined with plant simulation models and major computational models to be applied for water chemistry control are discussed.

Journal Articles

Corrosion of uranium and plutonium dioxides in aqueous solutions

Otobe, Haruyoshi; Kitatsuji, Yoshihiro; Kurata, Masaki; Takano, Masahide

Proceedings of 2014 Nuclear Plant Chemistry Conference (NPC 2014) (USB Flash Drive), 11 Pages, 2014/10

The chemical and transport behaviors of Pu and U in the corroded debris must be understood for the criticality safety control of Pu and U in the debris, especially for the removal operations and storage. Therefore, the chemical changes of UO$$_{2}$$ and PuO$$_{2}$$ powders, disks and U and Pu metal disks in H$$_{2}$$O$$_{2}$$ aqueous solution have been checked, where H$$_{2}$$O$$_{2}$$ is formed by the radiolysis of H$$_{2}$$O. As a result, UO$$_{2}$$ changed to hydrated uranium peroxide, whereas the PuO$$_{2}$$ remained unchanged. U metal was more reactive with H$$_{2}$$O$$_{2}$$ aqueous solution than Pu metal. The chemical changes of the mixed UO$$_{2}$$/PuO$$_{2}$$ powders in H$$_{2}$$O$$_{2}$$ aqueous solution have been investigated. The dried slurry of the middle zone of H$$_{2}$$O$$_{2}$$ aqueous solution was mainly composed of hydrated uranium peroxide, whereas the dried powder of the bottom zone was mainly composed of PuO$$_{2}$$.

Journal Articles

Evaluation of uncertainty associated with parameters for long-term safety assessments of geological disposal

Yamaguchi, Tetsuji; Minase, Naofumi; Iida, Yoshihisa; Tanaka, Tadao; Nakayama, Shinichi

JAERI-Conf 2005-007, p.150 - 155, 2005/08

no abstracts in English

Journal Articles

Additional function of JAERI Material Performance Database (JMPD) for Irradiation Assisted Stress Corrosion Cracking (IASCC) data

Kaji, Yoshiyuki; Tsukada, Takashi

Proceedings of 11th German-Japanese Workshop on Chemical Information, p.101 - 103, 2003/06

The JAERI Material Performance Database (JMPD) was developed with a view to utilizing material performance data efficiently. Data from more than 11,600 test pieces are prepared for data evaluation in the JMPD. Some kinds of data analyses for mechanical properties have been performed by utilizing the JMPD. Irradiation Assisted Stress Corrosion Cracking (IASCC) of austenitic stainless steels in high temperature water is considered to be one of the key issues for life assessment of the core internals of nuclear power plants. This paper describes the present status of the JMPD and additional function of JMPD for analysis of IASCC data.

JAEA Reports

Working Programme for MIU-4 Borehole Investigations

Ota, Kunio; Nakano, Katsushi; Metcalfe, R.; Ikeda, Koki; ; Amano, Kenji; Takeuchi, Shinji; Hama, Katsuhiro; Matsui, Hiroya

JNC TN7410 99-007, 44 Pages, 1999/08

JNC-TN7410-99-007.pdf:2.59MB

Journal Articles

Irradiation assisted stress corrosion cracking of austenitic stainless steels

Tsukada, Takashi

Proceedings of Seminar on Water Chemistry of Nuclear Reactor Systems '99, p.26 - 32, 1999/00

no abstracts in English

JAEA Reports

None

Okubo, Hiroo*

PNC TJ1222 97-002, 112 Pages, 1997/03

PNC-TJ1222-97-002.pdf:3.25MB

None

JAEA Reports

The Effects of water environments on crack growth behavior of LWR pressure vessel steels

Onizawa, Kunio; ; ;

JAERI-M 90-202, 33 Pages, 1990/11

JAERI-M-90-202.pdf:1.15MB

no abstracts in English

Oral presentation

Estimation method of long-term groundwater chemistry in granite

Iwatsuki, Teruki; Murakami, Hiroaki

no journal, , 

We reproduced the groundwater quality in granite up to a depth of about 1000m using the geochemical simulation code, and devised a method to identify the major minerals involved in the evolution of water quality. We also estimated the long-term water-rock interaction of these minerals based on groundwater ages.

Oral presentation

The Overview of research on Materials Evaluation Research Group and summary of experiments on fracture mechanics

Shimodaira, Masaki; Hata, Kuniki; Iwata, Keiko; Ha, Yoosung; Kasahara, Shigeki; Katsuyama, Jinya

no journal, , 

no abstracts in English

Oral presentation

The Effects of hydrogen addition on the corrosive conditions of PWR primary coolant under irradiation, 1; Effects radiation quality and pH on water radiolysis

Hata, Kuniki; Hanawa, Satoshi; Chimi, Yasuhiro; Uchida, Shunsuke

no journal, , 

no abstracts in English

Oral presentation

The Overview of research on Materials Evaluation Research Group and a study on the structural integrity assessment of reactor pressure vessels

Hata, Kuniki; Iwata, Keiko; Shimodaira, Masaki; Ha, Yoosung; Takamizawa, Hisashi; Katsuyama, Jinya

no journal, , 

no abstracts in English

Oral presentation

Application experiences of water chemistry standards and request for its revision, 1; Exchange of opinions for utilization and revision of water chemistry standards

Hanawa, Satoshi; Kawamura, Hirotaka*; Akamine, Hiroshi*; Shoda, Yasuhiko*; Nagase, Makoto*; Umehara, Ryuji*

no journal, , 

no abstracts in English

Oral presentation

Development of ECP analysis code for both BWR and PWR primary coolant loops

Hata, Kuniki; Uchida, Shunsuke*; Hanawa, Satoshi; Chimi, Yasuhiro; Sato, Tomonori

no journal, , 

no abstracts in English

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