Concrete benchmark experiment: ex-vessel LWR surveillance dosimetry
Description
The analysis of DOEL-1 in-vessel and ex-vessel neutron dosimetry, using the DOT 3.5 Sn code coupled with the VITAMIN-C cross-section library, showed the same C/E values for different detectors at the surveillance capsule and the ex-vessel cavity positions. These results seem to be in contradiction with those obtained in several Benchmark experiments (PCA, PSF, VENUS...) when using the same computational tools. Indeed a strong decreasing radial trend of the C/E was observed, partly explained by the overestimation of the iron inelastic scattering. The flat trend seen in DOEL-1 could be explained by compensating errors in the calculation such as the backscattering due to the concrete walls outside the cavity. The 'Concrete Benchmark' experiment has been designed to judge the ability of this calculation methods to treat the backscattering. This paper describes the 'Concrete Benchmark' experiment, the measured and computed neutron dosimetry results and their comparison. This preliminary analysis seems to indicate an overestimation of the backscattering effect in the calculations. (authors). 5 figs., 1 tab., 7 refs
Availability note (English)
MF available from INIS under the Report Number.Files
26052575.pdf
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Additional details
Additional titles
- Original title (French)
- Experience ''Benchmark beton'' pour la dosimetrie hors cuve dans les reacteurs a eau legere
Publishing Information
- Imprint Pagination
- 13 p.
- Report number
- EDF--94-NB-00064
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 26052575
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BACKSCATTERING; BENCHMARKS; D CODES; DOEL-1 REACTOR; NEUTRON DOSIMETRY; RADIATION DETECTORS; REACTOR CORES; REACTOR VESSELS
- Descriptors DEC
- COMPUTER CODES; CONTAINERS; DOSIMETRY; ENRICHED URANIUM REACTORS; MEASURING INSTRUMENTS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; SCATTERING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS