Dosimetry relating to steel irradiations in reactor MELUSINE
Creators
- 1. CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Service d'Etudes des Reacteurs et de Mathematiques Appliquees
- 2. CEA Centre d'Etudes Nucleaires de Grenoble, 38 (France). Service des Piles
Description
The knowledge of the neutron spectrum is absolutely necessary for the interpretation of the structure material irradiations. Because of the spectrum variations it is necessary to have the proper damage cross section for the comparison of the different irradiations. At Melusine, the neutron fluences are measured in the loops by the 63Cu(n,α) reaction for the irradiations steel reactor vessel. The study of the neutron spectra is obtained experimentally by the activation detectors In, Ni, Al and theoretically by the transport codes in two dimensions, ANISN-DOT III. The response of the different damage functions was calculated for these spectra. Result point out great sensitivity of spectrum indices and damage answers to rig structure and to source perturbations by close area
Additional details
Additional titles
- Original title (French)
- Dosimetrie relative a des irradiations dans le reacteur Melusine
Publishing Information
- Imprint Title
- Proceedings of the First ASTM-EURATOM symposium on reactor dosimetry. Petten, Netherlands, September 22-26, 1975
- Journal Page Range
- p. 69-80.
- 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
- 9395903
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- A CODES; DAMAGING NEUTRON FLUENCE; FAST NEUTRONS; MELUSINE-1 REACTOR; MULTIGROUP THEORY; NEUTRON DOSIMETRY; NEUTRONIC DAMAGE FUNCTIONS; SPATIAL DISTRIBUTION; STEELS
- Descriptors DEC
- ALLOYS; BARYONS; CARBON ADDITIONS; COMPUTER CODES; DISTRIBUTION; DOSIMETRY; ELEMENTARY PARTICLES; ENRICHED URANIUM REACTORS; FERMIONS; HADRONS; IRON ALLOYS; IRON BASE ALLOYS; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; NEUTRON FLUENCE; NEUTRONS; NUCLEONS; POOL TYPE REACTORS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; THERMAL REACTORS; TRAINING REACTORS; TRANSITION ELEMENT ALLOYS; TRANSPORT THEORY; WATER COOLED REACTORS; WATER MODERATED REACTORS