Published May 1976
| Version v1
Report
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The application of gamma and isotopic correlation techniques for safeguards identification and verification purposes
- 1. Atomova Elektraren Bohunice, Jaslovske Bohunice (Czechoslovakia)
Description
The report contains the method of measurement of burn-up and isotopic composition of spent fuel by the non-destructive gamma spectrometry method developed for the fuel elements of the Bohunice A-1 power plant. Results obtained for samples of spent fuel as well as fuel assemblies are shown. The method of measuring the radial distribution of the radioactive fission products is briefly described and examples demonstrating its use are given. In-core neutron flux mapping with self-powered detectors and burn-up determination by detector signal integration are also described
Availability note (English)
MF available from INIS under the Report Number.Files
8300020.pdf
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Additional details
Additional titles
- Subtitle (English)
- Final report for the period 15 November 1973 - 14 November 1975
Publishing Information
- Imprint Pagination
- 112 p.
- Report number
- IAEA-R--1443-F
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 8300020
- Subject category
- S98: NUCLEAR DISARMAMENT, SAFEGUARDS AND PHYSICAL PROTECTION;
- Descriptors DEI
- BOHUNICE A-1 REACTOR; BURNUP; GAMMA SPECTROSCOPY; IAEA SAFEGUARDS; ISOTOPE RATIO; LI-DRIFTED GE DETECTORS; NEUTRON FLUX; NONDESTRUCTIVE ANALYSIS; SELF-POWERED DETECTORS; SPENT FUEL ELEMENTS; TABLES
- Descriptors DEC
- CHEMICAL ANALYSIS; FUEL ELEMENTS; GAS COOLED REACTORS; GE SEMICONDUCTOR DETECTORS; HEAVY WATER MODERATED REACTORS; HWGCR TYPE REACTORS; INFORMATION; LI-DRIFTED DETECTORS; MEASURING INSTRUMENTS; NATURAL URANIUM REACTORS; POWER REACTORS; RADIATION DETECTORS; RADIATION FLUX; REACTOR COMPONENTS; REACTORS; SAFEGUARDS; SEMICONDUCTOR DETECTORS; SPECTROSCOPY; THERMAL REACTORS