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Journal Articles

Study of solvent degradation in reprocessing MOX spent fuel; Solvent degradation and its effect on Pu purification cycle

Kawaguchi, Yoshihito; Morimoto, Kazuyuki; Kitao, Takahiko; Oyama, Koichi; Omori, Eiichi

Nihon Genshiryoku Gakkai Wabun Rombunshi, 8(3), p.221 - 229, 2009/09

30% Tributyl phosphate (TBP)/n-dodecane is used on PUREX process in Tokai Reprocessing Plant (TRP). TBP is degraded to di-butyl phosphate (DBP), mono-butyl phosphate (MBP) etc. mainly caused by radiation, extracted element and hydrolysis. In this study, we studied TBP degradation kinetic equation, Pu concentration in high DBP concentration solution after stripping Pu from the solution by diluted HNO$$_{3}$$, DBP concentration in mixer-settler and effect for process while MOX spent fuel was reprocessed and operation was stopped with Pu loaded on solution for 20 days. As a result of this study, we obtained the equation of TBP degradation. Moreover, the maximum DBP concentration in mixer-settler while reprocessing MOX spent fuel was 91 ppm, DBP concentration while stopping operation was 2000 ppm and we found out there was nothing out of the ordinary on the process after the process was restarted.

JAEA Reports

PSA Application on the Tokai Reprocessing Plant

Takafumi, Nakano,; Ishida, Michihiko; Kazuyuki, Morimoto,; Inano, Masatoshi; Nojiri, Ichiro

JNC TN8410 2003-017, 190 Pages, 2004/03

JNC-TN8410-2003-017.pdf:6.61MB

Probabilistic Safety Assessment (PSA) methodology has been applied to evaluate the relative importance of safety functions that prevent the progress of event causing to postulate accidents.

Journal Articles

PSA Application on the Tokai Reprocessing Plant

Ishida, Michihiko; ; Kazuyuki, Morimoto,; Nojiri, Ichiro

Probabilistic Safety Assessment and Management, p.543 - 548, 2004/00

Probabilistic Safety Assessment (PSA) methodology has been applied on the Tokai Reprocessing Plant (TRP) to evaluate relative importance of safety functions that prevent the progress of events causing to postulated accidents. The relative importance of safety functions was evaluated by using two major importance measures, Fussell-Vesely and Risk Achievement Worth both generally used in PSA of nuclear power plants. Through these evaluations, some useful insights into the safety of the TRP have been obtained. The results of the relative importance measures would be utilized to qualify component/equipment as important safety function.

Oral presentation

Study of neptunium behavior in extraction process of Tokai reprocessing plant, 1; Results on balance of neptunium in extraction process

Nagaoka, Shinichi; Morimoto, Kazuyuki; Sato, Takehiko; Kanamori, Sadamu; Omori, Eiichi

no journal, , 

no abstracts in English

Oral presentation

Oral presentation

Three decades of forward steps and prospect in Tokai reprocessing plant, 5; Corrosion of equipments holding high-concentrated plutonium nitrate solution in Tokai reprocessing plant

Obu, Tomoyuki; Morimoto, Kazuyuki; Yoshinari, Toshimi; Kanamori, Sadamu; Omori, Eiichi

no journal, , 

no abstracts in English

Oral presentation

MOX reprocessing at TRP, 5; Evaluation for temperature of plutonium product in storage

Kurabayashi, Kazuaki; Kawaguchi, Yoshihito; Takaya, Akikazu; Morimoto, Kazuyuki; Kanamori, Sadamu; Omori, Eiichi

no journal, , 

Plutonium product recovered from Fugen MOX type B spent fuel is measured temperature at Tokai Reprocessing Plant. And we studied difference between estimated by ORIGEN and analytical value of relative promotion on Pu, moreover, we studied calculation model because of the difference between initial evaluation and temperature of Pu product.

Oral presentation

MOX reprocessing at TRP, 6; Study of solvent degradation

Hoshi, Takahiro; Kawaguchi, Yoshihito; Kitao, Takahiko; Oyama, Koichi; Morimoto, Kazuyuki; Kanamori, Sadamu; Omori, Eiichi

no journal, , 

For reprocessing nuclear spent fuel, in future, used for plutonium-thermal and fast-breeding reactor, density of DBP in extraction solvent on reprocessing Fugen MOX Type B fuel was measured. And we formulated an equation for increased density of DBP to estimate density of DBP in extraction cycle.

Oral presentation

MOX reprocessing at TRP, 4; Control test of Neptunium extraction

Kawakami, Yoshiyuki; Nagaoka, Shinichi; Kitao, Takahiko; Morimoto, Kazuyuki; Obu, Tomoyuki; Kanamori, Sadamu; Omori, Eiichi

no journal, , 

We are trying to research how acidity and temperature influences Np behavior at extraction process in Tokai Reprocessing Plant. So we varied acidity and warmed up solution within the limit of operating parameter for second extraction cycle, and measured Np extracted.

Oral presentation

Equipment integrity conformation of fast breeder prototype reactor MONJU, 5; EVST system sodium leak countermeasure work conformation test

Kawakami, Shodai; Morimoto, Kazuyuki; Hamano, Tomoharu; Oba, Toshio

no journal, , 

no abstracts in English

Oral presentation

Control test of neptunium extraction at Tokai reprocessing plant

Nagaoka, Shinichi; Morimoto, Kazuyuki; Kitao, Takahiko; Obu, Tomoyuki; Kanamori, Sadamu; Omori, Eiichi

no journal, , 

40$$sim$$50% of neptunium (Np) was distributed to product stream in Tokai Reprocessing Plant (TRP) at present. We tried to increase acidity of second extraction cycle within available operating parameter, and by measuring neptunium concentration at outlet stage in second extraction cycle, we verified that 60$$sim$$70% of neptunium was distributed to product stream. Also we warmed up solutions in contactors of second extraction cycle within available operating parameter to make sure oxidation of neptunium on actual process, and we verified that 70% of neptunium was distributed to product stream. We confirmed that increasing acidity and warming up solutions was effective for Pu-U-Np co-extraction on the engineering scale reprocessing facility.

Oral presentation

The Examination for applying salt-free solvent washing reagent to Tokai Reprocessing Plant

Yamamoto, Kohei; Kaji, Naoya; Morimoto, Kazuyuki; Obu, Tomoyuki; Sano, Yuichi; Kashimura, Takao

no journal, , 

no abstracts in English

Oral presentation

Liquid leakage from the sea release pipe of the Tokai reprocessing plant; Cause investigation of the leakage, 2; Progress from mechanical damage to the leak

Domura, Kazuyuki; Morimoto, Kenji; Seto, Nobuhiko; Iwasaki, Shogo; Fukuari, Yoshihiro; Inami, Shinichi

no journal, , 

A leak occurred from the sea release pipe buried in the bottom of the sea of the Tokai reprocessing plant. The plumbing of the leak point was cut to investigate the cause of the leak and was collected ashore. Then the investigations such as surface observation and other analyses were performed. As a result of this investigation, the plumbing was scratched at the time of construction from the outside. In the service of approximately 17 years, a damaged part changed with age, and it was estimated that it led to a crack. It was estimated for the leak of the plumbing that hydrogen produced with electrolytic protection caused hydrogen embrittlement cracking and hydrogen induced cracking. This paper reports the details of the investigations.

Oral presentation

Development of U and Pu co-recovery process, 1; Consideration of flow sheet composition and setting of flow sheet by MIXSET-X

Namatame, Toshihiro; Sato, Takehiko; Morimoto, Kazuyuki; Obu, Tomoyuki; Kashimura, Takao; Omori, Eiichi

no journal, , 

no abstracts in English

Oral presentation

Development of U and Pu co-recovery process, 2; Miniture mixer-settlers-tests based on setting flow sheet by MIXSET-X

Fujimoto, Ikuo; Yanagibashi, Futoshi; Akiyama, Hideki; Morimoto, Kazuyuki; Obu, Tomoyuki; Taki, Kiyotaka

no journal, , 

no abstracts in English

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