Published March 1977 | Version v1
Report Open

Status of neutron cross sections for reactor dosimetry

Creators

  • 1. International Atomic Energy Agency, Vienna (Austria)
  • 2. Centre d'Etude de l'Energie Nucleaire, Mol (Belgium)
  • 3. Hanford Engineering Development Lab., Richland, Wash. (USA)

Description

The status of current international efforts to develop standardized sets of evaluated energy-dependent (differential) neutron cross sections for reactor dosimetry is reviewed. The status and availability of differential data are considered, some recent results of the data testing of the ENDF/B-IV dosimetry file using 252Cf and 235U benchmark reference neutron fields are presented, and a brief review is given of the current efforts to characterize and identify dosimetry benchmark radiation fields

Availability note (English)

MF available from INIS under the Report Number.

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Additional details

Publishing Information

Imprint Pagination
53 p.
Report number
INDC(NDS)--84/L+M

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
8317575
Subject category
S73: NUCLEAR PHYSICS AND RADIATION PHYSICS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Descriptors DEI
BIBLIOGRAPHIES; DATA; DIAGRAMS; INTEGRAL CROSS SECTIONS; MEV RANGE 01-10; MEV RANGE 10-100; NEUTRON DOSIMETRY; NEUTRON REACTIONS; NEUTRON SPECTRA; REACTORS; SPONTANEOUS FISSION; THERMAL FISSION
Descriptors DEC
BARYON REACTIONS; CROSS SECTIONS; DOCUMENT TYPES; DOSIMETRY; ENERGY RANGE; FISSION; HADRON REACTIONS; INFORMATION; MEV RANGE; NUCLEAR REACTIONS; NUCLEON REACTIONS; SPECTRA