Published 2012
| Version v1
Journal article
Neutron field characterisation at mixed oxide fuel plant
- 1. Landauer, 2 Science Road, Glenwood, IL 60425-1586 (United States)
- 2. Landauer Europe, 33 Avenue du General Leclerc, 92266 Fontenay-aux-Roses Cedex (France)
- 3. Stillwater Crystal Growth Div., Landauer, 723 1/2 Eastgate St., Stillwater, OK 74074 (United States)
- 4. AREVA Melox, B.P. 93124, 30203 Bagnols-sur-Ceze, Cedex (France)
Description
A neutron field characterisation was conducted at the AREVA Melox Plant to determine the response of passive and active neutron dosemeters for several stages in the mixed oxide fuel manufacturing process. Landauer Europe provides radiation dosimetry to many contractors working at the Melox site. The studies were conducted to assist in determining the neutron radiation fields the workers are exposed to routinely, evaluate the need for specific neutron correction factors and to ensure that the most accurate neutron dose is reported for the Melox Plant workers. (authors)
Availability note (English)
Available from doi: http://dx.doi.org/10.1093/rpd/ncr390Additional details
Identifiers
- DOI
- 10.1093/rpd/ncr390;
Publishing Information
- Journal Title
- Radiation Protection Dosimetry
- Journal Volume
- 150
- Journal Issue
- 2
- Journal Page Range
- p. 231-238
- ISSN
- 0144-8420
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- France
- INIS RN
- 43085715
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- DOSEMETERS; DOSES; DOSIMETRY; MIXED OXIDE FUEL FABRICATION PLANTS; MIXED OXIDE FUELS; NEUTRONS
- Descriptors DEC
- BARYONS; ELEMENTARY PARTICLES; ENERGY SOURCES; FERMIONS; FUEL FABRICATION PLANTS; FUELS; HADRONS; MATERIALS; MEASURING INSTRUMENTS; NUCLEAR FACILITIES; NUCLEAR FUELS; NUCLEONS; REACTOR MATERIALS; SOLID FUELS
Optional Information
- Notes
- 13 refs