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Journal Articles

Maintenance management of emergency power supply equipment (uninterruptible power supply) in Tokai reprocessing plant

Nishida, Kyosuke; Hiyama, Hisao; Shibata, Satomi; Iwasaki, Shogo; Inami, Shinichi

Nihon Hozen Gakkai Dai-6-Kai Gakujutsu Koenkai Yoshishu, p.294 - 297, 2009/08

Uninterruptible power supply systems are installed in the Tokai reprocessing plant in preparation for the emergency case that the commercial power supply is stopped by an accidental or intentional interruption in the supply of electricity. The uninterruptible power supply system particularly provides a temporary power source to the important devices for the radiation control of nuclear critical monitoring in the plant. Thus, the system is potentially important and essential for nuclear plants. The paper repots the current activities such as regular inspections, replacement of parts and system update, to maintain the function of uninterruptible power supply systems.

Journal Articles

Batchwise distribution studies of actinides on TRUEX partitioning method by use of high level liquid waste

Sato, Soichi; Nishida, Kyosuke; Kuno, Yusuke; Masui, Jinichi; Yamanouchi, Takamichi; Yamamura, Osamu

GLOBAL '93, 0 Pages, 1993/00

None

JAEA Reports

Isotope correlation techniques for Tokai Reprocessing Plant safeguards (II); Evaluation of the four campaign date and heel correction

Nishida, Kyosuke*; *; *; *; *

PNC TN8410 89-034VOL1, 76 Pages, 1989/06

PNC-TN8410-89-034VOL1.pdf:2.92MB

Isotopic Correlation Techniques (ICTs) have been developed to verify the input accountability of reprocessing plant. Institute (JAERI) was introduced to the Tokai reprocessing plant of Power Reactor and Nuclear Fuel Developement Corporation (PNC) in 1985. Besides, that was inproved to be capable of automatically traneferring sorce data necessary for the calculation to the program by PNC. The result of data evaluation of the 1986 campaigns shown in the previous report suggested that reduction of precision be essential to apply the ICTs to the safeguards, because the scatter (1$$sigma$$) of the difference between measured value and ICTs' on batch-based verification was approximately 10%. The heel corrections, which should be the largest cause of the error, were dealt with in the report. As the results, the scatters of uranium and plutonium in the 86 - 1 campaign were reduced dramatically to 4 % and 5% , respectively, whereas those in the 86 - 2 campaign were 4% and 5% respectively.

JAEA Reports

JASPAS JC-3;High Resolution Gamma Spectrometer for Plutonium Isotopic Analysis Field Test of New TASTEX System for Plutonium Product Verification at The Tokai Repr

*; *; *; *; Nishida, Kyosuke*; *

PNC TN8410 88-038, 64 Pages, 1988/07

PNC-TN8410-88-038.pdf:3.47MB

This report describes the field test results of the New TASTEX system. This system consisting of the high resolution gamma spectrometer and the K-edge densitometer can measure both isotopic abundances and concentration of plutonium simultaneously. Entire system is controlled by the multi-channel analyser and a multi-user computer. The system was designed and built under the Japan Support Program for Agency Safeguards (JASPAS). The software of this system developed at Los Alamos National Laboratory (LANL) and Lawrence Livermore National Laboratory (LLNL) has been installed in the system assembled at the Tokai reprocessing plant(TRP) in July 1985. In the course of campaigns from 1985 till 1988, field tests have been carried out on plutonium product solutions of TRR. The results of plutonium concentration and isotopic abundances obtained by the K-edge densitometer and the high resolution gamma spectrometer (HRGS) have been compared with those by controlled potential coulometer and mass spectrometer respectively. Precision of plutonium determination with K-edge densitometer is estimated approximately 0.7% and 1.0% for the freshly processed plutonium and the aged plutonium respectively. The scatters in the relative differences between HRGS and the destructive analysis (DA) detected on the results of freshly processed plutonium sample were 1.6%, 0.4%, 0.5%, 1.1%, 8.0% for Pu-238, Pu-239, Pu-240, Pu-241, Pu-242 respectively, whereas those on the results of aged sample were 1.4%, 0.5%, 1.1%, 1.1% for Pu-238, Pu-239, Pu-240, Pu-241 respectively.

Journal Articles

None

Sato, Soichi; Nishida, Kyosuke; Kuno, Yusuke;

Donen Giho, , 

None

Journal Articles

None

Nishida, Kyosuke; Sato, Soichi; Kuno, Yusuke;

Donen Giho, , 

None

Oral presentation

Liquid leakage from the sea release pipe of the Tokai reprocessing plant; Cause investigation of the leakage, 3; Preventive measures against recurrences and the management method

Nishida, Kyosuke; Sukigara, Koji; Terunuma, Tomohiro; Iwasaki, Shogo; Inami, Shinichi

no journal, , 

no abstracts in English

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