Published 1993
| Version v1
Report
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Retrospective dosimetry (or self dosimetry): Application to French Nuclear Power Plants
Description
In this text we give the dosimetry principle on irradiated materials such baffle screw, pressure vessel and control element cans. This measure, made by gammametry, is based on the steel activation and comparison with calculated measures by Actige code. 4 figs., 6 refs
Availability note (English)
MF available from INIS under the Report Number.Files
25074097.pdf
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Additional details
Additional titles
- Original title (French)
- Dosimetrie retrospective (ou auto-dosimetrie): application au parc electronucleaire francais
Publishing Information
- Imprint Pagination
- 8 p.
- Report number
- CEA-CONF--11792
Conference
- Title
- Workshop on Pressure Vessel Surveillance Programmes and their Applications.
- Original Conference Title
- Seance de travail sur les programmes de surveillance des cuves et leurs applications
- Dates
- 16-18 Mar 1993.
- Place
- Prague (Czech Republic).
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 25074097
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACTIVATION DETECTORS; BAFFLES; CONTROL ELEMENTS; NEUTRON ACTIVATION ANALYSIS; NEUTRON DOSIMETRY; NEUTRON FLUENCE; NEUTRON FLUX; PRESSURE VESSELS; PWR TYPE REACTORS; STEELS
- Descriptors DEC
- ACTIVATION ANALYSIS; ALLOYS; CARBON ADDITIONS; CHEMICAL ANALYSIS; CONTAINERS; CONTROL EQUIPMENT; DOSIMETRY; ENRICHED URANIUM REACTORS; EQUIPMENT; FLOW REGULATORS; IRON ALLOYS; IRON BASE ALLOYS; MEASURING INSTRUMENTS; NEUTRON DETECTORS; NONDESTRUCTIVE ANALYSIS; POWER REACTORS; RADIATION DETECTORS; RADIATION FLUX; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS