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 In RFEF, BWR fuel rods were withdrawn from a fuel assembly irradiated for 5 cycles in the Fukushima-2 Nuclear Power Station Unit-1 and PIEs including nondestructive examination of those rods were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.

Evaluation of neutron irradiation embrittlement in structural materials for reactor pressure vessel

Ooka, Norikazu*; Ishii, Toshimitsu

Hihakai Kensa, 52(5), p.235 - 239, 2003/05

no abstracts in English

Detection of internal defect in materials by infrared thermography and its numerical simulation; Effect of thermal diffusivity of materials on defect detection

Ishii, Toshimitsu; Inagaki, Terumi*; Sakane, Taisuke*; Nakatani, Takahiko*; Ooka, Norikazu; Omi, Masao; Hoshiya, Taiji

Hihakai Kensa, 51(4), p.223 - 230, 2002/04

http://ci.nii.ac.jp/naid/10007951261

no abstracts in English

Development of advanced neutron radiography for inspection on irradiated fuels and materials, 3; Examination of neutron imaging plate and computed tomography methods on unirradiated fuel rod

Yasuda, Ryo; Matsubayashi, Masahito; Nakata, Masahito; Harada, Katsuya; Amano, Hidetoshi; Ando, Hitoshi*; Sasajima, Fumio; Nishi, Masahiro; Horiguchi, Yoji

JAERI-Tech 2002-001, 23 Pages, 2002/02

JAERI-Tech-2002-001.pdf:3.79MB

Advanced neutron radiography techniques such as neutron imaging plate (NIP) and Computed Tomography (CT) methods have been investigated the practicality for Post Irradiation Examination (PIE). In this work, an unirradiated fuel rod was examined by NIP and CT methods in order to collect the fundamental data for applying these techniques to PIE.The fuel rod is composed of seven-enriched UO2 pellet and two-natural UO2 pellet that are loaded into a Zircaloy tube. There are somewhat difference in the size and shape among those UO2 pellets. A transmitted and cross-sectional images were obtained by NIP and CT methods, respectively.In the NIP image, the difference in the size, shape, and enrichment among the UO2 pellets is obviously recognized. In the case of CT method, the images clearly show the detailed shape of the cross section in the pellets, in addition, the difference in the enrichment between the natural and enriched pellets is recognized.

Post irradiation examination of (U,Pu) C and (U,Pu) N fuel for fast reactor; Non-destructive examination result of the fuel pin

; ; ; Matsumoto, Shinichiro

JNC TN9410 2000-009, 65 Pages, 2000/09

JNC-TN9410-2000-009.pdf:4.36MB

In order to evaluate irradiation behavior of(U, Pu) C and (U, Pu) N fuel using fast reactor, (U, Pu) C and (U, Pu) N fuel pins were irradiated in JOYO for the fist time in Japan. In this study, one (U, Pu) C fuel pin and two (U, Pu) N fuel pins were irradiated to maximum burn up about 40GWd/t. Post irradiation examination of (U, Pu) C and (U, Pu) N fuel pins started in Fuel Monitoring Facility (FMF) at JNC from October 1999, and it ended in March, 2000. The results of non-destructive post irradiation examination reported in this document. Main results are shown in the following. (1)The soundness of all (U,Pu) C and (U,Pu) N fuel pins were confirmed from the non-destructive examination result. (2)The fuel stack elongation of (U,Pu) C and (U,Pu) N is bigger than it of the MOX fuel for fast reactor. (3)The singular behavior from the gamma ray scanning measurement in the stack area was not confirmed. The migration of Cs137 to lower insulator pellet and outside of the pellet was confirmed in (U,Pu) N B9NO2 pin. In (U,Pu) C fuel, the migration of Cs137 was not confirmed. (4)In (U,Pu) C B9CO1 pin and (U,Pu) N B9NO2 pin in which the gap width was small, diameter of cladding increase around 50 m in the stack area which originates for FCMI was confirmed. In (U,Pu) N B9NO1 pin in which the gap width was wide, the ovality which originates from the relocation of the pellet was confirmed. (5)Fission gas release rate of (U,Pu) N were 3.3% and 5.2%, and the low value compared to the MOX fuel was shown.

A Study on design methods for overpack welds; Acquisition of basic data to quantify welding quality

*; *; *; *; Sago, Hiromi*; *; *

JNC TJ8400 2000-049, 161 Pages, 2000/02

JNC-TJ8400-2000-049.pdf:9.56MB

In this study basic data on welds of overpack structures for HLW were acquired and a predictive destruction analysis was performed usig the data acquired, in order to examine the viability of weld design methods. The results are summarized as follows: (1)Investigation of Design and Welding Condition for Welded Joint Models. Three welding methods--EBW, TIG and MAG--were selected, and welding conditions were determined so that the welding quality almost equivalent to that of an actual over-pack was ensured. (2)Fabrication of Welded Joint Models. Three welded joint models, one for each of EBW, TIG and MAG, were fabricated. It was confirmed that these models satisfied the quality requirements for Class I specified in JIS Z3104. (3)Sampling and Machining of Strength Test Specimens. Test specimens were taken from each welded joint model, and models for corrosion tests were delivered to the Japan Nuclear Cycle Development Institute (JNC). (4)Strength Test and Micro/macro Structure observation. Tensile tests were conducted at room temperature and at 150C, and fracture toughness tests at 0C and 150C, in order to obtain stress-strain curves, J-R curves and Vickers hardness. In addition, an observation of micro and macro structures was performed. (5)Evaluation. Using the data on the welds obtained from the tests, a fracture prediction analysis and an evaluation of unstable fracture due to weld flaws were performed on the over-pack design described in the second progress report. The following conclusions were obtained: (a)For the overpack design examined, the effects of welds (material property and residual stress) and fabrication tolerance on fracture loading are negligible. (b)In addition, it was decided that even in a design with reduced wall thickness, welds have an insignificant effect on fracture loading because fracture initiates in the center of the shell of the overpack. (c)The size of flaws leading to unstable fracture is on ...

Newly developed non-destructive testing method for evaluation of irradiation brittleness of structural materials using ultrasonic

; Ooka, Norikazu; ; Saito, Junichi; Hoshiya, Taiji; *; Kobayashi, Hideo*

JAERI-Conf 99-009, p.163 - 172, 1999/09

https://jopss.jaea.go.jp/pdfdata/JAERI-Conf-99-009.pdf

no abstracts in English

None

; ; Ishibashi, Yuzo; Takeda, Seiichiro; *; Fujisaku, Kazuhiko*; *

PNC TN8410 98-116, 147 Pages, 1998/08

PNC-TN8410-98-116.pdf:8.42MB

None

None

Okubo, Seisuke*

PNC TJ1602 97-004, 141 Pages, 1997/03

PNC-TJ1602-97-004.pdf:4.31MB

no abstracts in English

Oxide layer-thickness measurement on fuel cladding for high burnup HBWR fuel rods using eddy current method (Non-destructive examination)

Nakata, Masahito; Amano, Hidetoshi; ; Nishi, Masahiro; Nakamura, Jinichi; Furuta, Teruo; ;

HPR-345, 0, 9 Pages, 1995/00

no abstracts in English