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JAEA Reports

Comparison between HTFP code and minory changed FORNAX-A code

Aihara, Jun; Ueta, Shohei; Goto, Minoru; Inaba, Yoshitomo; Shibata, Taiju; Ohashi, Hirofumi

JAEA-Technology 2018-002, 70 Pages, 2018/06

JAEA-Technology-2018-002.pdf:1.46MB

HTFP code is code for calculation of additional release amount of fission product (FP) from fuel rod in high temperature gas-cooled reactor (HTGR) after stop of fission. Minory changed Fornax-A code also can calculate that. Therefore, release behavior of Cs calculated with HTFP code was compared with that calculated with minory modified FORNAX-A code in this report. Release constants of Cs evaluated with minory modified FORNAX-A code are rather different from default values for HTFP code.

JAEA Reports

HTFP for calculation of amount of additionally released fission products from fuel rods of pin-in-block-type high temperature gas-cooled reactors during accident

Nomoto, Yasunobu; Aihara, Jun; Nakagawa, Shigeaki; Isaka, Kazuyoshi; Ohashi, Hirofumi

JAEA-Data/Code 2015-008, 39 Pages, 2015/06

JAEA-Data-Code-2015-008.pdf:10.32MB

HTFP is a calculation code for amount of additionally released fission product (FP) from fuel rods of pin-in-type according to transient of core temperature at the accident of high temperature gas-cooled reactors (HTGRs). This code analyzes FP release inventory from core according to the transient of core temperature at the accident as an input data and considering FP release rate from a fuel compact and a graphite sleeve and radioactive decay of FP. This report describes the outline of HTFP code and its input data. The computed solutions using the HTFP code were compared to those of HTCORE code, which was used for the design of the High Temperature Engineering Test Reactor (HTTR) to validate the analysis models of the HTFP code. The comparison of HTFP code results with HTCORE code results showed the good agreement.

Journal Articles

Fission gas release and swelling in uranium-plutonium mixed nitride fuels

Tanaka, Kosuke*; Maeda, Koji*; Katsuyama, Kozo*; Inoue, Masaki*; Iwai, Takashi; Arai, Yasuo

Journal of Nuclear Materials, 327(2-3), p.77 - 87, 2004/05

no abstracts in English

Journal Articles

Irradiation performance of uranium-plutonium mixed nitride fuel pins in JOYO

Inoue, Masaki*; Iwai, Takashi; Arai, Yasuo; Asaga, Takeo*

Proceedings of GLOBAL2003 Atoms for Prosperity; Updating Eisenhower's Global Vision for Nuclear Energy (CD-ROM), p.1694 - 1703, 2003/11

no abstracts in English

Journal Articles

Behavior of uranium-plutonium mixed carbide fuel irradiated at JOYO

Arai, Yasuo; Iwai, Takashi; Nakajima, Kunihisa; Nagashima, Hisao; Nihei, Yasuo; Katsuyama, Kozo*; Inoue, Masaki*

Proceedings of GLOBAL2003 Atoms for Prosperity; Updating Eisenhower's Global Vision for Nuclear Energy (CD-ROM), p.1686 - 1693, 2003/00

no abstracts in English

JAEA Reports

Light water reactor fuel analysis code FEMAXI-V(Ver.1)

Suzuki, Motoe

JAERI-Data/Code 2000-030, 280 Pages, 2000/09

JAERI-Data-Code-2000-030.pdf:11.06MB

no abstracts in English

Journal Articles

Analysis of high burnup fuel IFA-519.9 by EXBURN-I code

Suzuki, Motoe; Saito, Hioraki*

HPR-349, 12 Pages, 1998/00

no abstracts in English

JAEA Reports

Detailed description and user's manual of high burnup fuel analysis code EXBURN-I

Suzuki, Motoe; Saito, Hioraki*

JAERI-Data/Code 97-046, 210 Pages, 1997/11

JAERI-Data-Code-97-046.pdf:5.41MB

no abstracts in English

JAEA Reports

Light water reactor fuel analysis code FEMAXI-IV, 2; Detailed structure and user's manual

Suzuki, Motoe; Saito, Hioraki*

JAERI-Data/Code 97-043, 235 Pages, 1997/11

JAERI-Data-Code-97-043.pdf:5.84MB

no abstracts in English

JAEA Reports

Description and user's manual of light water reactor fuel analysis code FEMAXI-IV (Ver.2)

Suzuki, Motoe; Saito, Hioraki*

JAERI-Data/Code 97-010, 221 Pages, 1997/03

JAERI-Data-Code-97-010.pdf:6.28MB

no abstracts in English

JAEA Reports

Plate-out distribution of iodine in a high temperature gas cooling in-pile loop facility

Matsumoto, Mikio; Endo, Yasuichi; ; Itabashi, Yukio; ; Yokouchi, Iichiro; Ando, Hiroei

JAERI-M 92-212, 62 Pages, 1993/01

JAERI-M-92-212.pdf:2.09MB

no abstracts in English

Journal Articles

Study on the behavior of PWR fuel during reactivity initiated accident conditions, II; Influence of FP gas release

Yanagisawa, Kazuaki

Nihon Genshiryoku Gakkai-Shi, 32(4), p.385 - 394, 1990/04

 Times Cited Count:1 Percentile:19.38(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Study of pellet-cladding interaction on light water reactor fuel, (I); PWR type fuel rod

; ; E.Kolstad*

Nihon Genshiryoku Gakkai-Shi, 28(7), p.641 - 657, 1986/00

 Times Cited Count:4 Percentile:47.77(Nuclear Science & Technology)

no abstracts in English

13 (Records 1-13 displayed on this page)
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