Published 1980 | Version v1
Report

Dosimetry results for Big Ten and related benchmarks

  • 1. Los Alamos Scientific Lab., NM (USA)
  • 2. National Bureau of Standards, Gaithersburg, MD (USA)

Description

Measured average reaction cross sections for the Big Ten central flux spectrum are given together with calculated values based on the U.S. Evaluated Nuclear Data File ENDF/B-IV. Central reactivity coefficients for 233U, 235U, 239Pu, 6Li and 10B are given to check consistency of bias between measured and calculated reaction cross sections for these isotopes. Spectral indexes for the Los Alamos 233U, 235U and 239Pu metal critical assemblies are updated, utilizing the Big Ten measurements and interassembly calibrations, and their implications for inelastic scattering are reiterated

Part of:
Dosimetry methods for fuels, cladding and structural materials

Additional details

Publishing Information

ISBN
92-825-1868-X
Imprint Title
Dosimetry methods for fuels, cladding and structural materials
Imprint Pagination
642 p.
Journal Page Range
p. 989-997.
Report number
EUR--6813(v.2)

Conference

Title
3. ASTM-EURATOM symposium on reactor dosimetry.
Dates
1 - 5 Oct 1979.
Place
Ispra, Italy.

INIS

Country of Publication
European Commission (EC), Brussels (Belgium)
Country of Input or Organization
European Commission (EC), Brussels (Belgium)
INIS RN
12587260
Subject category
S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
Resource subtype / Literary indicator
Conference, Numerical Data
Descriptors DEI
BENCHMARKS; BIG TEN REACTOR; COMPUTER CALCULATIONS; EXPERIMENTAL DATA; FISSION RATIO; INTEGRAL CROSS SECTIONS; NEUTRON DOSIMETRY; NEUTRON FLUX; NEUTRON REACTIONS; NEUTRON SPECTRA; REACTIVITY COEFFICIENTS
Descriptors DEC
BARYON REACTIONS; CROSS SECTIONS; DATA; DOSIMETRY; EXPERIMENTAL REACTORS; HADRON REACTIONS; INFORMATION; NUCLEAR REACTIONS; NUCLEON REACTIONS; NUMERICAL DATA; RADIATION FLUX; REACTORS; RESEARCH AND TEST REACTORS; SPECTRA; ZERO POWER REACTORS

Optional Information