Published 1977
| Version v1
Report
Open
Analysis of dose rates near the circuit of a PWR after shutdown
Creators
- 1. CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Service d'Etudes des Reacteurs et de Mathematiques Appliquees
Description
From activities measured and calculated in the primary circuit of the CHOOZ reactor, gamma dose rates corresponding to individual corrosion product isotope deposits have been determined. These dose rates are compared with experimental results. Contributions of gamma sources deposited in different regions of the steam generators to the dose inside the 'channel head' have been evaluated
Availability note (English)
MF available from INIS under the Report Number.Files
9395806.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 7 p.
- Report number
- CEA-CONF--3965
Conference
- Title
- 5. International conference on reactor shielding.
- Dates
- 18 - 22 Apr 1977.
- Place
- Knoxville, Tenn., USA.
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 9395806
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ARDENNES REACTOR; CONTAMINATION; CORROSION PRODUCTS; DOSE RATES; M CODES; PRIMARY COOLANT CIRCUITS; REACTOR SHUTDOWN; STEAM GENERATORS
- Descriptors DEC
- BOILERS; COMPUTER CODES; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS