Published 1979 | Version v1
Report

Benchmark tests of JENDL-1 for structural materials

Creators

  • 1. Power Reactor and Nuclear Fuel Development Corp., Tokyo (Japan)

Description

In order ot examine the reliability of JENDL-1 for its use of FBR core design, various benchmark tests were performed on the basis of selected integral measurements. Total of 21 assemblies were selected and sample worths were calculated for 10B, Cr, Fe, Ni, C, Na, Al and Mo. The adjustment technique was applied for the cross sections to fit the experimental values. Besides, fast neutron spectra in Fe were calculated and then compared with the measurements at KURRI to evaluate the JENDL-1 data for structural materials

Additional details

Publishing Information

ISBN
0-08-023424-0
Imprint Title
Neutron data of structural materials for fast reactors
Journal Page Range
p. 105-117.
Report number
EUR--6108

Conference

Title
Specialists' meeting on neutron data of structural materials for fast reactors.
Dates
5 - 8 Dec 1977.
Place
Geel, Belgium.

INIS

Country of Publication
European Commission (EC), Brussels (Belgium)
Country of Input or Organization
European Commission (EC), Brussels (Belgium)
INIS RN
10495014
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
Resource subtype / Literary indicator
Conference, Numerical Data, Non-conventional Literature
Descriptors DEI
ALUMINIUM; BORON 10; CARBON; CHROMIUM; EXPERIMENTAL DATA; GRAPHS; IRON; LMFBR TYPE REACTORS; MOLYBDENUM; NEUTRON SPECTRA; NICKEL; REACTIVITY WORTHS; REACTOR MATERIALS; SODIUM
Descriptors DEC
ALKALI METALS; BORON ISOTOPES; BREEDER REACTORS; DATA; DATA FORMS; ELEMENTS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; INFORMATION; ISOTOPES; LIGHT NUCLEI; LIQUID METAL COOLED REACTORS; METALS; NONMETALS; NUCLEI; NUMERICAL DATA; ODD-ODD NUCLEI; REACTORS; SPECTRA; STABLE ISOTOPES; TRANSITION ELEMENTS