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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 $$sim$$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.

JAEA Reports

None

Kato, Masato

PNC-TN8600 94-005, 132 Pages, 1994/08

PNC-TN8600-94-005.pdf:7.95MB

no abstracts in English

JAEA Reports

None

Kato, Masato

PNC-TN8600 94-004, 184 Pages, 1994/08

PNC-TN8600-94-004.pdf:9.48MB

no abstracts in English

Journal Articles

Macroscopic calculational model of fission gas release from water reactor fuels

Uchida, Masaaki

Journal of Nuclear Science and Technology, 30(8), p.752 - 761, 1993/08

 Times Cited Count:2 Percentile:68.67(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

JAEA Reports

JAEA Reports

JAEA Reports

Temperature Analysis of Coated-Fuel-Particle Capsule Irradiated in JRR-2 In-Core Position

; ; Iwamoto, K.

JAERI-M 6908, 16 Pages, 1977/01

JAERI-M-6908.pdf:0.97MB

no abstracts in English

JAEA Reports

Thermal Calculation of Short Fuel Pin Capsules

JAERI-M 5469, 58 Pages, 1973/12

JAERI-M-5469.pdf:1.35MB

no abstracts in English

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