Published March 1998 | Version v1
Report Metadata-only

Analysis of reactivity characteristics of the MONJU initial core using JENDL-3.2

Creators

  • 1. Power Reactor and Nuclear Fuel Development Corp., Tsuruga, Fukui (Japan). Monju Construction Office

Description

This paper describes the evaluated results of criticality, absorber rod worth and coolant worth in the MONJU initial cores based on the JENDL-3.2 library compared with those of the JENDL-2 library. We confirm that the ratios of calculated and experimental (C/E) values using the JENDL-3.2 library are slightly better than those based on the JENDL-2 library. (author)

Part of:
Proceedings of the 1997 symposium on nuclear data

Additional details

Publishing Information

Imprint Title
Proceedings of the 1997 symposium on nuclear data
Imprint Pagination
372 p.
Journal Page Range
p. 73-78
Report number
JAERI-Conf--98-003

Conference

Title
1997 symposium on nuclear data
Dates
27-28 Nov 1997
Place
Tokai, Ibaraki (Japan)

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
29046806
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ACTIVATION ANALYSIS; BENCHMARKS; CONTROL ROD WORTHS; GROUP CONSTANTS; MONJU REACTOR; MULTIPLICATION FACTORS; NUCLEAR DATA COLLECTIONS; REACTIVITY WORTHS; SENSITIVITY ANALYSIS
Descriptors DEC
BREEDER REACTORS; CHEMICAL ANALYSIS; CROSS SECTIONS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; NONDESTRUCTIVE ANALYSIS; POWER REACTORS; REACTORS; SODIUM COOLED REACTORS

Optional Information

Secondary number(s)
INDC(JPN)--180/U