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JAEA Reports

Criticality safety evaluation in Tokai reprocessing plant

Shirai, Nobutoshi; ; ; Shirozu, Hidetomo; ; Hayashi, Shinichiro;

JNC-TN8410 2000-006, 116 Pages, 2000/04

JNC-TN8410-2000-006.pdf:2.77MB

Criticality limits for equipments in Tokai Reprocessing Plant which handle fissile material solution and are under shape and dimension control were reevaluated based on the guideline No.10 "Criticality safety of single unit" in the regulatory guide for reprocessing plant safety. This report presents criticality safety evaluation of each equipment as single unit. Criticality safety of multiple units in a cell or a room was also evaluated. The evaluated equipments were ones in dissolution, separation, purification, denitration, Pu product storage, and Pu conversion processes. As a result, it was reconfirmed that the equipments were safe enough from a view point of criticality safety of single unit and multiple units.

Journal Articles

Mock-up tests for design of silver mediated electrolytic dissolver

Sugikawa, Susumu; ; Takeshita, Isao; *; *; *; P.Bretault*; R.Vialard*; M.Lecomte*

Proc. of 5th Int. Nucl. Conf. on Recycling, Conditioning and Disposal (RECOD '98), 3, p.931 - 938, 1998/00

no abstracts in English

Journal Articles

The Life prediction study of Rokkasho Reprocessing plant materials

Kiuchi, Kiyoshi; Yano, Masaya*; *;

Proc. of 5th Int. Nucl. Conf. on Recycling, Conditioning and Disposal (RECOD '98), 3, 8 Pages, 1998/00

no abstracts in English

JAEA Reports

Outline of a fuel treatment facility in NUCEF

Sugikawa, Susumu; ; ; Nakazaki, Masato; Shirahashi, Koichi; ; *; *; Tsuji, Kenichi*; Tachimori, Shoichi; et al.

JAERI-Tech 97-007, 86 Pages, 1997/03

JAERI-Tech-97-007.pdf:3.27MB

no abstracts in English

JAEA Reports

A Study of safety margins in criticality safety analysis of a dissolution process

Yamamoto, Toshihiro; *

JAERI-M 93-218, 18 Pages, 1993/11

JAERI-M-93-218.pdf:0.67MB

no abstracts in English

JAEA Reports

None

PNC-TN1700 93-006, 24 Pages, 1993/01

PNC-TN1700-93-006.pdf:0.27MB

no abstracts in English

Journal Articles

Non-destructive and destructive measurements on burnup characteristics of Japan Power Demonstration Reactor-I full-core fuel assemblies

; ; ; ; ; ; ; ; ; ; et al.

Journal of Nuclear Science and Technology, 23(1), p.53 - 72, 1986/00

 Times Cited Count:8 Percentile:31.29(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

None

Gonda, Kozo; *; *

PNC-TN841 79-06, 27 Pages, 1979/02

PNC-TN841-79-06.pdf:0.5MB

no abstracts in English

Oral presentation

Remote wall thickness measurement of the fuel basket of the dissolver

Yokota, Satoru; Hatanaka, Akira; Fujimori, Masahito; Shimoyamada, Tetsuya; Nakamura, Yoshinobu

no journal, , 

Three batch-type dissolvers in the Tokai Reprocessing Plant are a device for dissolving spent fuel. The dissolver is composed of one slab and two barrels (stainless steel 310s). Install a fuel basket (stainless steel 304L) in the barrel and accept the sheared spent fuel to dissolve it. The insoluble fuel cladding is taken out of the barrels with the basket. The dissolution time of operation for one batch is approximately 10 hours. During dissolution operation, nitric acid was added to the dissolver into the spent fuel in the basket with water. The solution was heated with steam. Corrosion failure has occurred in the past because the dissolver is exposed to a high corrosive environment (high temperature, high acid concentration). Therefore, we carry out the periodical wall thickness measurement of the barrel by the remote control. On the other hand, the wall thickness measurement of the fuel basket was carried out only once by destructive measurement at the time of renewal in 1999. The details of the corrosion tendency of the fuel basket are unknown, and it is urgent to establish a non-destructive measurement method by remote handling. Therefore, we examined the method of wall thickness measurement of the fuel basket and established the measuring technique.

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