Published April 1982 | Version v1
Report

Displacement damage calculations with ENDF/B-V

  • 1. Argonne National Lab., IL (USA)

Description

Neutron displacement damage cross sections have been calculated for 30 elements using nuclear cross sections from ENDF/B-V. Six elements have been extended to 44 MeV for accelerator-based neutron sources. Spectral-averaged damage cross sections are found to agree within 10% of those calculated previously using ENDF/B-IV. Nuclear data is needed to improve the quality of the files and to provide for error assignments. The treatment of some reactions also needs improvement, especially (n,γ), β-decay, and secondary-particle emission above 14 MeV. (author)

Additional details

Publishing Information

Imprint Title
Nuclear data for radiation damage assessment and related safety aspects
Imprint Pagination
337 p.
Journal Page Range
p. 185-192.
Report number
IAEA-TECDOC--263

Conference

Title
Advisory group meeting on nuclear data for radiation damage assessment and related safety aspects.
Dates
12 - 16 Oct 1981.
Place
Vienna (Austria).

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
14741445
Subject category
S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTER CALCULATIONS; CROSS SECTIONS; D CODES; DISLOCATIONS; ELEMENTS; NEUTRON REACTIONS; NEUTRON SPECTRA; PHYSICAL RADIATION EFFECTS
Descriptors DEC
BARYON REACTIONS; COMPUTER CODES; CRYSTAL DEFECTS; CRYSTAL STRUCTURE; HADRON REACTIONS; LINE DEFECTS; NUCLEAR REACTIONS; NUCLEON REACTIONS; RADIATION EFFECTS; SPECTRA