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Journal Articles

Analysis of actual work process related with the JCO criticality accident

Tanabe, Fumiya; Yamaguchi, Yukichi

Nippon Genshiryoku Gakkai-Shi, 43(1), p.52 - 55, 2001/01

 Times Cited Count:1 Percentile:86.43(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

None

*

JNC-TJ6420 2000-005, 109 Pages, 2000/07

JNC-TJ6420-2000-005.pdf:3.16MB

no abstracts in English

JAEA Reports

Desgin study of pyrochemical process operation by using virtual engineering models

; Tozawa, Katsuhiro; ; ; *

JNC-TN9400 2000-053, 99 Pages, 2000/04

JNC-TN9400-2000-053.pdf:7.47MB

This report describes accomplishment of simulations of Pyrochemical Process Operation by using virtual engineering models. The pyrochemical process using molten salt electrorefining would introduce new technologies for new fuels of particle oxide, particle nitride and metallic fuels. This system is a batch treatment system of reprocessing and re-fabrication, which transports products of solid form from a process to next process. As a result, this system needs automated transport system for process operations by robotics. ln this study, a simulation code system has been prepared, which provides virtual engineering environment to evaluate the pyrochemical process operation of a batch treatment system using handling robots. And the simulation study has been conducted to evaluate the required system functions, which are the function of handling robots, the interactions between robot and process equipment, and the time schedule of process, in the automated transport system by robotics. As a result of simulation of the process operation, which we have designed, the automated transport system by robotics of the pyrochemical process is realistic. And the issues for the system development have been pointed out.

JAEA Reports

Operation system concept for high-level radioactive wastes disposal facility

*; *; Tanai, Kenji

JNC-TN8400 99-050, 94 Pages, 1999/11

JNC-TN8400-99-050.pdf:3.86MB

This paper reports on the evaluations of operational activities for a High Level Radioactive Wastes Disposal Facility, from initial acceptance of vitrified waste at a surface facility to emplacement engineered barriers in underground facilities. The purpose of this analysis is to confirm the technical feasibility of geological disposal. First, the basic design and repository system requirements are identified. Second, operational activities in surface facilities, access facilities and underground facilities are described. The required procedures and equipment, suitable for specific emplacement concepts and configurations for engineered barrier systems are discussed for specific examples. Countermeasures for potential adverse events or conditions are based on extensive civil engineering and mining experiences in Japan and abroad. The time schedule is also evaluated on the basis of these concepts. In addition, the concept of stationary and mobile radiation control areas is studied based on experiences and practice in current nuclear facilities. Finally future research and development items are summarized.

JAEA Reports

Investigations on repository layouts

Tanai, Kenji; Iwasa, Kengo; Hasegawa, Hiroshi; Goke, Mitsuo*; Horita, Masakuni*; Noda, Masaru*

JNC-TN8400 99-044, 140 Pages, 1999/11

JNC-TN8400-99-044.pdf:7.85MB

This report consists of three items: (1)Study of the repository configuration, (2)Study of the surface facilities configuration for construction, operation and buckfilling, (3)Planning schedule, In the repository configuration, the basic factors influencing the design of the repository configuration are presented, and the results of studies of various possible repository configurations are presented for both hard and soft rock systems. Here, the minimum conditions regarding geological environment required to guide design are assumed, because it is difficult to determine the repository configuration without considering specific conditions of a disposal site. In the surface facility configuration, it is illustrated based on the results of construction, operation, buckfilling studies for underground disposal facility and EIS report of CANADA. In the schedule, the overall schedule corresponding to the repository layout is outlined in link with the milestone of disposal schedule set forth in the government's basic policy. The assumptions and the basic conditions are summarized to examine the General Schedule from start of construction to closure of a repository. This summaly is based on the technologies to be used for construction, operation and closure of a repository. The basic national policies form the framework for this review of the general schedule.

JAEA Reports

Assessment on the mechanical stability of underground excavations

; ; Koo, Shigeru*; Hasegawa, Hiroshi; ; Kubota, Shigeru*; *

JNC-TN8400 99-037, 281 Pages, 1999/11

JNC-TN8400-99-037.pdf:15.51MB

It is planned to construct the tunnels and emplace waste packages at several hundred meters to 1,000 meters under the ground for the repository of high-level radioactive waste based on a policy to assure the safe life environment. It is required to be mechanically stable for the tunnels to assure the work safety throughout the construction, operation and closure phase. In this report, the mechanical stability of tunnels, that is a factor of design requisites, was evaluated by the analyses to present an outline of the technical reliability of geological disposal. To put it concretely, the tunnel sections were determined to have the required areas and shapes, and the analyses on the mechanical stability at tunnel excavations and earthquake, at tunnel intersections were conducted by the theoretical analysis and finite element method. The results obtained by these investigations are shown below: (1)It will be able to construct the tunnels with present techniques. The mechanical stability of tunnels will be assured if proper supports are given, and adequate tunnel spacing and disposal-pit pitches are set. (2)The mechanical stability will be assured at the tunnels intersections if proper reinforcement measures are taken. The reinforcement will be required for the intersection areas over the distance of 1D (D: diameter of tunnels) on the obtuse angle side, and 4D on the acute angle side, when intersection angle is set at 30 degrees. (3)The investigations were conducted on the assumption that the experienced big earthquake occurred. The results show that the effect of earthquake on the mechanical stability of tunnels is small, and tunnels are stable at the earthquake when the mechanical stability at tunnel excavations is assured.

JAEA Reports

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.

JAEA Reports

None

PNC-TN1410 93-019, 40 Pages, 1993/04

PNC-TN1410-93-019.pdf:1.35MB

no abstracts in English

JAEA Reports

None

;

PNC-TN8410 92-167, 51 Pages, 1992/09

PNC-TN8410-92-167.pdf:1.03MB

None

JAEA Reports

None

Power Reactor and Nuclear Fuel Development Corporation

PNC-TN9360 91-002, 110 Pages, 1991/08

PNC-TN9360-91-002.pdf:4.67MB

no abstracts in English

JAEA Reports

None

; ; *; *; Arii, Yoshio; ;

PNC-TN9520 91-007, 54 Pages, 1991/06

PNC-TN9520-91-007.pdf:1.43MB

None

JAEA Reports

None

Kusama, Tomoko*; Kai, Michiaki*

PNC-TJ1602 91-002, 14 Pages, 1991/03

PNC-TJ1602-91-002.pdf:0.45MB

no abstracts in English

JAEA Reports

None

Power Reactor and Nuclear Fuel Development Corporation

PNC-TN9360 91-001, 83 Pages, 1991/01

PNC-TN9360-91-001.pdf:3.6MB

no abstracts in English

JAEA Reports

None

PNC-TJ9349 88-001VOL1, 188 Pages, 1988/12

PNC-TJ9349-88-001VOL1.pdf:5.71MB

None

JAEA Reports

None

PNC-TN1410 97-025, 53 Pages, 1988/03

PNC-TN1410-97-025.pdf:2.09MB

no abstracts in English

JAEA Reports

Conelptual Design of Krypton Recovery Plant by Prous Membrone Method

; ; Shimizu, Toku; Saito, Keiichiro; ; ; *; Naruse, Yuji

JAERI-M 8494, 291 Pages, 1979/10

JAERI-M-8494.pdf:7.21MB

no abstracts in English

16 (Records 1-16 displayed on this page)
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