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