Differential neutron data for reactor dosimetry
Creators
Description
The present ENDF/B file for dosimetry consists of 36 reactions on 26 nuclides and was issued with Version IV of the ENDF/B library. This file of evaluated differential cross sections and the establishment of some neutron standard spectra form a first step towards a standardization in reactor dosimetry work. Furtheron a few published compilations and evaluations of neutron-induced reaction cross sections for dosimetry purposes are compared with respect to coverage and data presentation. Any up-dating of all these files can now be well accomplished through the help of the four cooperating data centers and national and international working groups. Finally the presently known experimental activities for differential cross section measurements and some current developments are brief
Additional details
Publishing Information
- Imprint Title
- Proceedings of the First ASTM-EURATOM symposium on reactor dosimetry. Petten, Netherlands, September 22-26, 1975
- Journal Page Range
- p. 93-111.
- Report number
- EUR--5667(pt.2)
Conference
- Title
- developments and standardization.
- Acronym
- 1. International symposium on reactor dosimetry
- Dates
- 22 - 26 Sep 1975.
- Place
- Petten, Netherlands.
INIS
- Country of Publication
- European Commission (EC), Brussels (Belgium)
- Country of Input or Organization
- European Commission (EC), Brussels (Belgium)
- INIS RN
- 9396179
- Subject category
- S99: GENERAL AND MISCELLANEOUS; S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CALIBRATION STANDARDS; DATA COMPILATION; DIFFERENTIAL CROSS SECTIONS; IN PILE LOOPS; NEUTRON DOSIMETRY; NEUTRON REACTIONS
- Descriptors DEC
- BARYON REACTIONS; CROSS SECTIONS; DOSIMETRY; HADRON REACTIONS; NUCLEAR REACTIONS; NUCLEON REACTIONS; REACTOR COMPONENTS; REACTOR EXPERIMENTAL FACILITIE