Published 1977 | Version v1
Report Metadata-only

Neutron flux density spectra of interest to reactor neutron metrology

Creators

Description

This document presents a collection of neutron flux density spectra of interest to reactor neutron metrology. The flux density spectra are shown in a series of figures, while values of group flux densities are presented too. For each spectrum the average energy and the average neutron speed is calculated. Also some damage characteristics of the spectra are included in the tables. No special normalization of the spectra was applied

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. 468-683.
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
10422659
Subject category
S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ALUMINIUM; DAMAGING NEUTRON FLUENCE; ENERGY DEPENDENCE; FAST NEUTRONS; FLUX DENSITY; GRAPHITE; NEUTRON DOSIMETRY; NEUTRON SPECTRA; STEELS; THERMAL NEUTRONS
Descriptors DEC
ALLOYS; BARYONS; CARBON; CARBON ADDITIONS; DOSIMETRY; ELEMENTARY PARTICLES; ELEMENTS; FERMIONS; HADRONS; IRON ALLOYS; IRON BASE ALLOYS; METALS; NEUTRON FLUENCE; NEUTRONS; NONMETALS; NUCLEONS; SPECTRA; TRANSITION ELEMENT ALLOYS