Annual report on operation, utilization and technical development of Hot Laboratories; From April 1, 2004 to March 31, 2005

Department of Hot Laboratories

JAERI-Review 2005-047, 95 Pages, 2005/09

JAERI-Review-2005-047.pdf:6.27MB

This is an annual report in 2004 fiscal year that describes activities of the Reactor Fuel Examination Facility (RFEF), the Waste Safety Testing Facility (WASTEF), and the Research Hot Laboratory (RHL) in the Department of Hot laboratories. In RFEF, BWR fuel rods were withdrawn from a fuel assembly irradiated for 5 cycles in the Fukushima-2 Nuclear Power Station Unit-1 and PIEs including nondestructive examination of those rods were carried out. In WASTEF, Slow Strain Rate Tests for detecting the susceptibility to IASCC, the corrosion test of reprocessing plant materials, tests for evaluating barrier performance in terms of waste disposal were performed. A secondary system pipe from the Mihama Nuclear Power Station Unit-3 was accepted to inspect the ageing fracture of it. In RHL, 15 lead cells are dismantled under the decommissioning plan at JAERI Tokai. And an arrangement of the RHL facility was started to use the storage of unirradiated nuclear materials.

Fabrication of saturated temperature capsule for IASCC study

Ishikawa, Kazuyoshi; Kikuchi, Taiji; Isozaki, Futoshi*; Inoue, Hiromi; Oba, Toshihiro; Matsui, Yoshinori; Saito, Takashi; Nakano, Junichi; Tsuji, Hirokazu

JAERI-Tech 2002-061, 69 Pages, 2002/08

JAERI-Tech-2002-061.pdf:12.21MB

Study of irradiation assisted stress corrosion cracking (IASCC) is an important subject for the plant life assessment and extension of the light water reactors (LWRs). It is necessary that initiation mechanism of IASCC should be made clear under combined effect of irradiation, environment and stress in order to understand IASCC phenomena. Under the existing circumstance, Saturated Temperature Capsule (SATCAP) were fabricated for the irradiation test of IASCC studies in Japan Material Testing Reactor (JMTR). SATCAP is the irradiation rig to irradiate materials in high pressure water of controlled chemistry and temperature simulating Boiling water reactors (BWRs) core environment from the new water feelding system of out-of-pile. This report describes (1) investigation of technical problems for the design and fabrication of SATCAP, (2) the tests results of the problems and (3) fabrication and inspection of SATCAP.

The Design study of the JT-60SU device, No.10; Auxiliary system, plan of displacement, and dismantlement・construction

; Masaki, Kei; Kaminaga, Atsushi; *; Kikuchi, Mitsuru; *; Miya, Naoyuki; Mori, Katsuharu*;

JAERI-Research 97-008, 146 Pages, 1997/02

JAERI-Research-97-008.pdf:4.6MB

no abstracts in English

Development of thermocouple re-instrumentation technique for irradiated fuel rod; Techniques for making center hole into UO pellets and thermocouple re-instrumentation to fuel rod

; Saito, Junichi; ; Endo, Yasuichi; ; Nakagawa, Tetsuya; ; Kawamata, Kazuo; ; Kawamura, Hiroshi; et al.

JAERI-Tech 95-037, 87 Pages, 1995/07

JAERI-Tech-95-037.pdf:5.14MB

no abstracts in English

None

Okada, Toshio; *; *; *; *; Miyake, Osamu; Sasaki, Shuichi

PNC TN1410 94-006, 57 Pages, 1994/11

PNC-TN1410-94-006.pdf:10.29MB

no abstracts in English

Present status of post-irradiation examinations on fuel in JMTR Hot Laboratory

Nakagawa, Tetsuya; ; ; Kawamata, Kazuo; ;

Proc. of 4th Asian Symp. on Research Reactors, 10 Pages, 1993/00

no abstracts in English

Large Co Sources Test Production by JRR-3 Reactor

; ; Genka, Tsuguo;

JAERI-M 5568, 58 Pages, 1974/02

JAERI-M-5568.pdf:2.42MB

no abstracts in English

Time history response analysis by assembly structural analysis

Nakajima, Norihiro; Nishida, Akemi; Kawakami, Yoshiaki; Tsuruta, Osamu; Suzuki, Yoshio

no journal, , 

Japan Atomic Energy Agency has been developing the three-dimensional virtual shaking table for earthquake-resistant evaluations in the atomic energy facilities. It is to realize an earthquake proofing reliability examination by analyzing the earthquake-resistant of the large structure on a computer. This is the trial that is going to realize a virtual shaking table examination such as difficult size of the original structures or nuclear power generation facilities while driving on a computer. Authors develop the structure analysis cord of the assembling structure so called FIESTA (Finite Element Structural Analysis for Assembly) as one of the core functions. This is the details analytical method that paid its attention to the behavior between the part of the assembling structure as one means to perform the earthquake-resistant evaluations for such as atomic energy facilities. In this report, it is reported the way of time history response analysis by assembly structural analysis.

Certainty in results of structural analysis

Nakajima, Norihiro; Nishida, Akemi; Kawakami, Yoshiaki; Suzuki, Yoshio

no journal, , 

Quality Assurance is an issue for computational science and engineering. It is well discussed in verification and validation for Simulation. In finite element analysis, it is a problem whether the finite element discretization is appropriate or not. Also, algorithmic choice prepared variously by the recent R&D discipline that become the problem which one to take. An experiment was performed for the static analysis and natural frequency analysis to confirm how uncertainty is revealed. As a result, by means to compare accuracy of the calculation precision that utilized a parallel environment, the numerical experiment reconfirmed that the estimate of the calculation solution was possible.

Towards to V and V for assembly structural analysis

Nakajima, Norihiro; Nishida, Akemi; Iigaki, Kazuhiko; Sawa, Kazuhiro

no journal, , 

An tried-out for the comparison with the observation and computational data is introduced. The simulation is carried out on the K by using an assembly structural analysis, so named FIESTA. The observation were determined in the high temperature engineering test reactor.