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Journal Articles

Phenomena identification ranking tables for accident tolerant fuel designs applicable to severe accident conditions

Khatib-Rahbar, M.*; Barrachin, M.*; Denning, R.*; Gabor, J.*; Gauntt, R.*; Herranz, L. E.*; Hobbins, R.*; Jacquemain, D.*; Maruyama, Yu; Metcalf, J.*; et al.

NUREG/CR-7282, ERI/NRC 21-204 (Internet), 160 Pages, 2021/04

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

Application of FORNAX-A

Aihara, Jun; Ueta, Shohei; Nishihara, Tetsuo

JAEA-Technology 2015-040, 32 Pages, 2016/02

JAEA-Technology-2015-040.pdf:0.83MB

Original FORNAX-A is a calculation code for amount of fission product (FP) released from fuel rods of pin-in-type high temperature gas-cooled reactors (HTGRs). This report is for explanation what calculations become possible with minor changed FORNAX-A.

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

Maintenance methods and procedures for the power conversion system of the Gas Turbine High Temperature Reactor 300 (GTHTR300)

Kosugiyama, Shinichi; Takei, Masanobu; Takizuka, Takakazu; Takada, Shoji; Yan, X.; Kunitomi, Kazuhiko

Nihon Genshiryoku Gakkai Wabun Rombunshi, 2(4), p.532 - 545, 2003/12

no abstracts in English

JAEA Reports

Study of prediction of fission product behaviours in severe accident; Scoping experiment and basic findings of Cs, Ba and Sr

; J.Huang*; ; ; ; Yamaguchi, Kenji*; Sugimoto, Jun

JAERI-Tech 98-003, 32 Pages, 1998/02

JAERI-Tech-98-003.pdf:1.12MB

no abstracts in English

Journal Articles

Irradiation behavior of microspheres of U-Zr alloys

Ogawa, Toru; ; Ito, Akinori; ; Sekino, Hajime; Nishi, Masahiro; Ishikawa, Akiyoshi; Akabori, Mitsuo

Journal of Alloys and Compounds, 271-273, p.670 - 675, 1998/00

 Times Cited Count:9 Percentile:54.62(Chemistry, Physical)

no abstracts in English

JAEA Reports

CORCON-Mod3 analysis of SURC experiments on molten core concrete interaction

J.Yan*; Maruyama, Yu; Sugimoto, Jun

JAERI-Tech 95-052, 27 Pages, 1995/12

JAERI-Tech-95-052.pdf:1.32MB

no abstracts in English

JAEA Reports

A Study of silver behavior in gas-turbine high temperature gas-cooled reactor

Sawa, Kazuhiro; Tanaka, Toshiyuki

JAERI-Research 95-071, 23 Pages, 1995/11

JAERI-Research-95-071.pdf:0.53MB

no abstracts in English

JAEA Reports

Irradiation experiments of the 6th$$sim$$12th OGL-1 Fuel Assemblies

Hayashi, Kimio; Minato, Kazuo; Kobayashi, Fumiaki; ; Fukuda, Kosaku; Kikuchi, Teruo; ;

JAERI-Research 94-017, 250 Pages, 1994/10

JAERI-Research-94-017.pdf:17.08MB

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

Verification of fission product release model from High Temperature Engineering Test Reactor fuel

Sawa, Kazuhiro; Shiozawa, Shusaku; Fukuda, Kosaku;

Journal of Nuclear Science and Technology, 29(9), p.842 - 850, 1992/09

no abstracts in English

Journal Articles

Studies of transient fission product gas release and PCMI of PWR fuel preirradiated to 39MWd/kgU

Yanagisawa, Kazuaki; Katanishi, Shoji; Sasajima, Hideo; ;

Proc. of the Int. Topical Meeting on LWR Fuel Performance; Fuel for the 90s, p.850 - 861, 1991/00

no abstracts in English

JAEA Reports

Outline of an experimental apparatus for the study on the advanced voloxidation process

Uchiyama, Gunzo; ; ; ; Sugikawa, Susumu; Maeda, Mitsuru; Tsujino, Takeshi

JAERI-M 90-016, 71 Pages, 1990/02

JAERI-M-90-016.pdf:1.88MB

no abstracts in English

JAEA Reports

Irradiation Experiments of Coted Particle Fuels by Gas-Swept Capsules,(II); Irradiation by 75F4A and 75F5A Capsules

; ; ; Tobita, Tsutomu; Minato, Kazuo; Yamamoto, Katsumune; ;

JAERI-M 87-020, 79 Pages, 1987/02

JAERI-M-87-020.pdf:4.96MB

no abstracts in English

JAEA Reports

Irradiafion Experiments of 3rd, 4th and 5th Fuel Blocks by an In-pile Gas Loop OGL-1

; ; ; Minato, Kazuo; ; ; ; Iwamoto, K.; Ikawa, Katsuichi

JAERI-M 86-092, 286 Pages, 1986/07

JAERI-M-86-092.pdf:23.75MB

no abstracts in English

JAEA Reports

VHTR Fuel Irradiation Tests by the In-pile Gas Loop,OGL-1 at JMTR

; ; ; ;

JAERI-M 86-068, 17 Pages, 1986/04

JAERI-M-86-068.pdf:0.8MB

no abstracts in English

JAEA Reports

Release of Metal Fission Products from Coated Particle Fuel (Sweep-Gas Capsules 74F9J,75F4A,and 75F5A)

; ; ; Tobita, Tsutomu; ; ; ; ; ; Iwamoto, K.; et al.

JAERI-M 85-041, 48 Pages, 1985/03

JAERI-M-85-041.pdf:1.33MB

no abstracts in English

JAEA Reports

Irradiation Test of The 1st and 2nd OGL-1 Fuel Assemblies

Ikawa, Katsuichi; ; ; ; ; Minato, Kazuo; Iwamoto, K.; ; ;

JAERI-M 83-012, 251 Pages, 1983/03

JAERI-M-83-012.pdf:17.56MB

no abstracts in English

JAEA Reports

24 (Records 1-20 displayed on this page)