Annual report of STACY operation in FY. 2000; Experiments on neutron-interacting systems with two slab-shaped core tanks and 10% enriched uranyl nitrate solution, 2 (Contract research)

Onodera, Seiji; Hirose, Hideyuki; Izawa, Kazuhiko; Tanino, Shuichi; Kaminaga, Jota*; Sakuraba, Koichi; Miyauchi, Masakatsu; Tonoike, Kotaro; Miyoshi, Yoshinori; Yanagisawa, Hiroshi; et al.

JAERI-Tech 2001-057, 54 Pages, 2001/09

JAERI-Tech-2001-057.pdf:4.28MB

no abstracts in English

Operation and maintenance experience on the fuel handling systems and storage facilities of "MONJU", 1

; ; ; ; ; ; Kaito, Yasuaki; ; ; ; et al.

PNC-TN2410 96-005, 339 Pages, 1996/03

PNC-TN2410-96-005.pdf:14.53MB

Construction of the 'Monju' fuel handling systems was completed in April, 1992. From March 1991 to August 1992, pre-commissioning tests were carried out. In December 1992, all the systems of Monju were transfered to PNC, and commissioning tests and reactor physics tests, were started. For the first time, during these physics tests, the fuel handling systems were operated for one of the commissioning tests 'Loading to Criticality', without significant problems. 168 fuel sub-assemblies were loaded into the core and the first criticality was achieved on 5th April 1994. The fuel handling systems continued in operation for the 'Loading to Full Size of the Core', power distribution test and for cleaning discharged dummy sub-assemblies. To keep these fuel handling systems working somothly and satisfactorily annual maintenance has been carried out since 1992. This paper describes the operation and maintenance experience of fuel handling systems after the pre-commissioning tests and future study items for system reliability improvement.

Study on the main design parameters of large scale-up fast breeder reactor (II); Study on fuel handling system (II)

*; *; Nakanishi, Seiji; *; *

PNC-TN9410 88-111, 134 Pages, 1988/08

PNC-TN9410-88-111.pdf:8.74MB

In order to rationalize the fuel handling system of Large Scale-up Fast Breeder Reactor, the equipment design of the Ex-vessel Storage (EVS) type fuel handling system was conducted in 1986. It can be considered that EVS type is coordinate with in-Vessel Storage (IVS) type from a viewpoint of materials and advantageous to Large Scale-up Fast Breeder Reactor for (1) reduction of reactor vessel diameter, (2) removal of the fuel handling process from sodium environment to water, and (3) realizationof ex-vessel NIS. As concerns sodium pot EVS type, the heat removal analysis at normal and transient conditions was performed to confirm the adequacy of the results gained from the equipment design in 1986 and to investigate requirements for the system. It was confirmed from the analysis results that the design was adequate and the requirements were extracted.

IAEA report on 'A predictive panel for the burn-up of a thermal neutron reactor'

Nippon Genshiryoku Gakkai-Shi, 9(8), p.485 - 486, 1967/00

no abstracts in English