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Journal Articles

Experience of integrated safeguards approach for large-scale hot cell laboratory

Miyaji, Noriko; Kawakami, Yukio; Koizumi, Atsuhiro; Otsuji, Ayako*; Sasaki, Keiichi*

IAEA-CN-184/60 (Internet), 6 Pages, 2010/11

http://www.iaea.org/Public/root/SG_SYMPOSIUM/Documents/PapersRepository/060.pdf

FMF at Oarai Research and Development Center (JNC-2 site) conducts post irradiation examinations (PIE) of fuel assemblies irradiated in Joyo. After the PIEs, the tested material is shipped back to a Joyo spent fuel pond. For the IAEA to apply the integrated safeguards approach (ISA) to the FMF, a new verification system on material transfer between Joyo and the FMF has been established. Gross defect verification of the nuclear material contained in the cask is performed at the time of short notice random interim inspections (RIIs) by measuring the surface neutron dose rate of the cask, filled with water to reduce radiation. As the result of performing a series of preliminary tests, this system could be used for the verification purpose under the ISA. It is clear that application of the system under the ISA provides the transparency of the material shipping and receiving process would be improved.

JAEA Reports

Improvement on core assembly irradiation bowing analysis method; Irradiation bowing analysis of JOYO inner reflector

Kikuchi, Shin; ; Ito, Kunihiro*

JNC TN9400 99-084, 92 Pages, 1999/12

JNC-TN9400-99-084.pdf:4.46MB

It is important to understand the deformation behaviors of core assembly in the aspect of the assembly life and the increase of removal load of assembly. Therefore, deformation behaviors of core assembly code: "BEACON" was being developed in order to evaluate these behaviors. However, there is a problem that the irradiation bowing modes and displacements of the JOYO assemblies obtained by the analysis were so different from the PIE data. In this study, the analysis condition, the application of analysis code and model were investigated through analysis on the JOYO Inner Reflector assembly based on PIE data.

JAEA Reports

Power-to-melt evaluation of fresh mixed-oxide fast reactor fuel; Technicall improvements of the post-irradiation-experiment and the evaluation of the results for the power-to-melt test FTM-2 in "JOYO"

; ;

JNC TN9400 2000-029, 87 Pages, 1999/11

JNC-TN9400-2000-029.pdf:5.11MB

The second Power-To-Melt (PTM) test, PTM-2, was performed in the experimental fast reactor "JOYO". AIl of the twenty-four fuel pins of the irradiation vehicle, B5D-2, for the PTM-2 test, were provided for post-irradiation-experiment (PIE) to evaluate the PTM values. ln this study, the PIE technique for PTM test was established and the PTM results were evaluated. The findings are as follows: (1) The maximum fuel-melting ratio on the transverse section was 10.7%, and was within the limit of fuel-melting in this PTM test enough. Unexpected fuel-melting amount to a ratio of 11.8% was found at 24 mm below the peak power elevation in a test fuel pin, lt is possible that this arose from secondary fuel-melting. (2) Combination of metallographical observation with X-ray microanalysis of plutonium distribution was very effective for the identification of once-molten fuel zone. (3) The PTM evaluation suggested that dependence of the PTM on the fuel pellet density was stronger than that of previous foreign PTM tests, while the dependence on the pellet-cladding gap and the oxygen-to-metal ratio was indistinctly. The dependence on the cladding temperature and the fill gas composition was not shown as well.