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JAEA Reports

DELIGHT-8; One dimensional fuel cell burnup analysis code for High Temperature Gas-cooled Reactor (HTGR) (Joint research)

Nojiri, Naoki; Fujimoto, Nozomu; Mori, Tomoaki; Obata, Hiroyuki*

JAERI-Data/Code 2004-012, 65 Pages, 2004/10

JAERI-Data-Code-2004-012.pdf:7.77MB

DELIGHT code is a fuel cell burnup analysis code which can produce the group constants necessary for High Temperature Gas-cooled Reactors (HTGR) core analyses. Collision probability method is used to the lattice calculation. The lattice calculation model is a cylinder type fuel or a ball type fuel of the HTGR. This code characterizes the burnup calculation considering the double heterogeneity caused by coated fuel particles of the HTGR fuel. DELIGHT code has updated its nuclear data library to the latest JENDL-3.3 data, and included new burnup chain models in order to calculate high burnup HTGR cores. The material regions of the periphery burnable poisons (BPs) were divided into details in order to improve calculation accuracy of the BP lattice calculation. This report presents the revised points of the DELIGHT-8 and can be used as user's manual.

Journal Articles

Evaluation of Delayed Neutron Data for JENDL-3.3

Yoshida, Tadashi*; Okajima, Shigeaki; Sakurai, Takeshi; Nakajima, Ken; Yamane, Tsuyoshi; Katakura, Junichi; Tahara, Yoshihisa*; Zukeran, Atsushi*; Oyamatsu, Kazuhiro*; Osawa, Takaaki*; et al.

Journal of Nuclear Science and Technology, 39(Suppl.2), p.136 - 139, 2002/08

http://wwwndc.jaea.go.jp/nd2001/proc/pdf/1_0136.pdf

no abstracts in English

JAEA Reports

Temperature dependence of lattice vibrations and analysis of specific heat in graphite (Cooperative research)

Nihira, Takeshi*; Iwata, Tadao*; Iwase, Akihiro

JAERI-Research 2001-045, 33 Pages, 2001/11

JAERI-Research-2001-045.pdf:1.27MB

no abstracts in English

Journal Articles

JSSTDL-300: The Standard shielding cross section library based on JENDL-3.2

Hasegawa, Akira; Yamano, Naoki*

Journal of Nuclear Science and Technology, 37(Suppl.1), p.723 - 727, 2000/03

https://doi.org/10.1080/00223131.2000.10874984

no abstracts in English

JAEA Reports

A New library of gamma rays group constants for BERMUDA based on JENDL-3.2 nuclear data file

; ; Suzuki, Tomoo*

JAERI-Data/Code 96-021, 33 Pages, 1996/06

JAERI-Data-Code-96-021.pdf:1.18MB

no abstracts in English

JAEA Reports

A New library of neutron group constants for BERMUDA based on JENDL-3.2 nuclear data file

; ; Suzuki, Tomoo

JAERI-Data/Code 95-006, 98 Pages, 1995/06

JAERI-Data-Code-95-006.pdf:2.92MB

no abstracts in English

Journal Articles

Numerical analysis on thermal-hydraulics of ribbed fuel rods for HTGRs,II; A Case with 2 dimensional square ribs

Takase, Kazuyuki; Akino, Norio

Kikai Gakkai Ibaraki Koenkai Koen Rombunshu, 0, p.127 - 128, 1995/00

no abstracts in English

JAEA Reports

Generation and verification of the multigroup constants library MGCL-J3 for nuclear criticality calculations

Komuro, Yuichi; Okuno, Hiroshi; Naito, Yoshitaka; *; Nagai, Masakatsu*; *; *; *

JAERI-M 93-190, 94 Pages, 1993/10

JAERI-M-93-190.pdf:1.86MB

no abstracts in English

JAEA Reports

Reactor Engineering Department annual report; April 1, 1992 March 31, 1993

JAERI-M 93-181, 247 Pages, 1993/09

JAERI-M-93-181.pdf:7.72MB

no abstracts in English

JAEA Reports

Reactor Engineering Department annual report; April 1, 1991 March 31, 1992

JAERI-M 92-125, 259 Pages, 1992/08

JAERI-M-92-125.pdf:8.22MB

no abstracts in English

Journal Articles

Lattice instability of premartensitic $_{1}$ phase in Cu $_{3}$ Al(+Pd) alloy under uniaxial pressure

*; *; Morii, Yukio; ; Funahashi, Satoru

Mater. Trans. JIM, 33(3), p.203 - 207, 1992/03

https://doi.org/10.2320/matertrans1989.33.203

Times Cited Count：17 Percentile：75.69(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Development of a common nuclear group constants library system; JSSTDL-295n-104 based on JENDL-3 nuclear data library

Nuclear Data for Science and Technology, p.232 - 234, 1992/00

no abstracts in English

JAEA Reports

Reactor Engineering Department annual report; April 1, 1990 March 31, 1991

JAERI-M 91-138, 262 Pages, 1991/09

JAERI-M-91-138.pdf:7.08MB

no abstracts in English

JAEA Reports

Production and accuracy evaluation of standard group constants for safety analysis of radiation shielding

Yamano, Naoki*; Tabara, Takashi*; ; Masukawa, Fumihiro; Naito, Yoshitaka

JAERI-M 90-183, 142 Pages, 1990/10

JAERI-M-90-183.pdf:3.28MB

no abstracts in English

JAEA Reports

Reactor Engineering Department annual report; April 1, 1989 March 31, 1990

JAERI-M 90-149, 330 Pages, 1990/09

JAERI-M-90-149.pdf:9.32MB

no abstracts in English

JAEA Reports

MAIL 3.0; A Computer program calculating cross sections for SIMCRI, ANISN, KENO-IV, MULTI-KENO and MULTI-KENO-II

Komuro, Yuichi; Okuno, Hiroshi; Naito, Yoshitaka; *; *; *

JAERI-M 90-126, 125 Pages, 1990/08

JAERI-M-90-126.pdf:2.18MB

no abstracts in English

JAEA Reports

DELIGHT-7; One dimensional fuel cell burnup analysis code for High Temperature Gas-Cooled Reactors (HTGR)

Shindo, Ryuichi; Yamashita, Kiyonobu; Murata, Isao

JAERI-M 90-048, 225 Pages, 1990/03

JAERI-M-90-048.pdf:5.06MB

no abstracts in English

Journal Articles

Application of potential constants; Empirical determination of molecular energy components for diatomic molecules, II

Spectrochimica Acta, Part A, 46(10), p.1461 - 1473, 1990/00

no abstracts in English

JAEA Reports

Evaluation of effective delayed neutron fraction and prompt neutron life time for High Temperature Engineering Test Reactor(HTTR)

Yamashita, Kiyonobu; Shindo, Ryuichi; Murata, Isao; Nakata, Tetsuo*

JAERI-M 89-198, 42 Pages, 1989/12

JAERI-M-89-198.pdf:1.01MB

no abstracts in English

JAEA Reports

Reactor Engineering Department annual report, April 1,1988 - March 31,1989

JAERI-M 89-128, 257 Pages, 1989/09

JAERI-M-89-128.pdf:6.94MB

no abstracts in English

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DELIGHT-8; One dimensional fuel cell burnup analysis code for High Temperature Gas-cooled Reactor (HTGR) (Joint research)

Evaluation of Delayed Neutron Data for JENDL-3.3

Temperature dependence of lattice vibrations and analysis of specific heat in graphite (Cooperative research)

JSSTDL-300: The Standard shielding cross section library based on JENDL-3.2

A New library of gamma rays group constants for BERMUDA based on JENDL-3.2 nuclear data file

A New library of neutron group constants for BERMUDA based on JENDL-3.2 nuclear data file

Numerical analysis on thermal-hydraulics of ribbed fuel rods for HTGRs,II; A Case with 2 dimensional square ribs

Generation and verification of the multigroup constants library MGCL-J3 for nuclear criticality calculations

Reactor Engineering Department annual report; April 1, 1992 March 31, 1993

Reactor Engineering Department annual report; April 1, 1991 March 31, 1992

Lattice instability of premartensitic $_{1}$ phase in Cu $_{3}$ Al(+Pd) alloy under uniaxial pressure

Development of a common nuclear group constants library system; JSSTDL-295n-104 based on JENDL-3 nuclear data library

Reactor Engineering Department annual report; April 1, 1990 March 31, 1991

Production and accuracy evaluation of standard group constants for safety analysis of radiation shielding

Reactor Engineering Department annual report; April 1, 1989 March 31, 1990

MAIL 3.0; A Computer program calculating cross sections for SIMCRI, ANISN, KENO-IV, MULTI-KENO and MULTI-KENO-II

DELIGHT-7; One dimensional fuel cell burnup analysis code for High Temperature Gas-Cooled Reactors (HTGR)

Application of potential constants; Empirical determination of molecular energy components for diatomic molecules, II

Evaluation of effective delayed neutron fraction and prompt neutron life time for High Temperature Engineering Test Reactor(HTTR)

Reactor Engineering Department annual report, April 1,1988 - March 31,1989