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.

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

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

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

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

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

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

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

DELIGHT-6(Revised) One Dimensional Lattice Burn-up Code for High Temperature Gas Cooled Reactors

;

JAERI-M 85-163, 78 Pages, 1985/10

JAERI-M-85-163.pdf:2.33MB

no abstracts in English

SLAROM:A code for cell homogenization calculation of fast reactor

Nakagawa, Masayuki;

JAERI 1294, 82 Pages, 1984/12

JAERI-1294.pdf:3.12MB

no abstracts in English