Published 1977 | Version v1
Report

Neutron fluence measurements applied to reactor materials irradiation

Creators

Description

Outgoing from the needs for neutron fluence measurements in the field of reactor material irradiations, a general review of the measuring methods is presented, including the discussion of their specific advantages and drawbacks. The application of the activation detector method is treated in more detail; special points are the choice of certain detector reactions, resp. materials, corrections and evaluation. Post-irradiation processing and measurement of the activated detectors is described. Concluding, selected monitoring problems and their treatment is discussed, like the monitoring of High-Temperature Reactor material irradiations and the demands for monitoring of radiation damage investigations

Additional details

Additional titles

Original title (German)
Neutronen-Fluenzmessungen zur Anwendung bei Bestrahlungen von Reaktorwerkstoffen

Publishing Information

Imprint Title
Proceedings of the First ASTM-EURATOM symposium on reactor dosimetry. Petten, Netherlands, September 22-26, 1975
Journal Page Range
p. 649-674.
Report number
EUR--5667(pt.1)

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
9393883
Subject category
S73: NUCLEAR PHYSICS AND RADIATION PHYSICS; S46: INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ACTIVATION DETECTORS; HTGR TYPE REACTORS; NEUTRON DOSIMETRY; NEUTRON FLUENCE; REACTOR MATERIALS; REVIEWS
Descriptors DEC
DOCUMENT TYPES; DOSIMETRY; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; MEASURING INSTRUMENTS; NEUTRON DETECTORS; RADIATION DETECTORS; REACTORS