Published October 22, 1979 | Version v1
Journal article Metadata-only

Status of neutron dosimetry and damage analysis for the fusion materials program

Creators

  • 1. Argonne Natl Lab, Ill

Description

The status of neutron flux and spectral measurements is described for fusion material irradiations at reactor, T(d,n), Be(d,n), and spallation neutron sources. Such measurements are required for the characterization of an irradiation in terms of displacement damage, gas and transmutant production. Emphasis is placed on nuclear data deficiencies with specific recommendations for cross section measurements and calculations. 12 refs

Additional details

Publishing Information

Journal Title
Natl. Bur. Stand. (U.S.), Spec. Publ.
Journal Issue
p. 812-816
Series
Natl. Bur. Stand. (U.S.), Spec. Publ.
ISSN
0083-1883

Conference

Title
Annual conference of the American Association for the Advancement of Science.
Dates
4 Jan 1980.
Place
San Francisco, CA, USA.

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
13670253
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CROSS SECTIONS; NEUTRON DOSIMETRY; PHYSICAL RADIATION EFFECTS; THERMONUCLEAR REACTOR MATERIAL
Descriptors DEC
DOSIMETRY; RADIATION EFFECTS

Optional Information

Secondary number(s)
CONF-800111--.