Published August 2002 | Version v1
Book Metadata-only

Development of one group constant library for the computer code ORIGEN-2 using JENDL-3.2

Creators

  • 1. NAIS Corp., Tokai, Ibaraki (Japan)

Description

Standard one group constant libraries for the ORIGEN-2 code are prepared using JENDL-3.2 for calculating the amount of nuclides generated in spent fuel of BWR, PWR and FBR, and the adaptability of the libraries is examined for the safety evaluation of the nuclear fuel cycle. This task is performed as a part of the activities of the nuclide generation evaluation working group of Japanese Nuclear Data Committee. (author)

Availability note (English)

Available from the Internet at URL https://doi.org/10.1080/00223131.2002.10875268
Part of:
Proceedings of the international conference on nuclear data for science and technology

Additional details

Identifiers

DOI
10.1080/00223131.2002.10875268;

Publishing Information

Publisher
Atomic Energy Society of Japan
Imprint Place
Tokyo (Japan)
Imprint Title
Proceedings of the international conference on nuclear data for science and technology
Imprint Pagination
1547 p.
Journal Page Range
p. 994-997

Conference

Title
International conference on nuclear data for science and technology
Acronym
ND 2001
Dates
7-12 Oct 2001
Place
Tsukuba, Ibaraki (Japan)

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
51063306
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BURNUP; BWR TYPE REACTORS; EVALUATION; FBR TYPE REACTORS; FUEL CYCLE; GROUP CONSTANTS; ISOTOPES; MIXED OXIDE FUELS; O CODES; PWR TYPE REACTORS; SAFETY; URANIUM DIOXIDE
Descriptors DEC
ACTINIDE COMPOUNDS; BREEDER REACTORS; CHALCOGENIDES; COMPUTER CODES; CROSS SECTIONS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FUELS; MATERIALS; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; POWER REACTORS; REACTOR MATERIALS; REACTORS; SOLID FUELS; THERMAL REACTORS; URANIUM COMPOUNDS; URANIUM OXIDES; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
2 refs., 4 figs., 4 tabs.; This record replaces 34024855 Imprint:Published as supplement 2 of Journal of Nuclear Science and Technology in 2 volumes