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Accurate determination and benchmarking of radiation field parameters relevant forpressure vessel monitoring. A review of some REDOS project results

Autor: OMera, B., Boehmer, B., Ballesteros, A., Konheiser, J., Kyncl, J., Hordosy, G., Keresztúri, A., Belousov, S., Ilieva, K., Kirilova, D., Mitev, M., Smutný, V., Polke, E., Zaritsky, S., Töre, C., Ortego, P.

Publikováno v: Journal of ASTM International 4(2007)10
12 th International Symposium on Reactor Dosimetry, 08.-13.05.2005, Gatlinburg, United States, 08.-13.05.2005, Gatlinburg, United StatesReactor Dosimetry: 12th International Symposium, West Conshohocken: ASTM, 978-0-8031-3412-6
Twelfth International Symposium on Reactor Dosimetry, 08.-13.05.2005, Gatlinburg, Tennesse, United States

Plant life management needs a reliable estimation of radiation field parameters, including their uncertainty, to avoid the use of conservative approaches. The particular objectives of the REDOS project are the improvements of the RPV monitoring, the

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::d380fa901372febd67e41531ac834b12
https://www.hzdr.de/publications/Publ-7782-2

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Reactor dosimetry: accurate determination and benchmarking of radiation field parameter, relevant for pressure vessel monitoring (REDOS) - REDOS Final Report

Autor: Ballesteros, A., Jardí, X., Böhmer, B., Konheiser, J., OMera, B., Kyncl, J., Keresztúri, A., Hordosy, G., Ilieva, K., Belousov, S., Kirilova, D., Mitev, M., Petrov, B., Acosta, B., Smutný, V., Polke, E., Zaritsky, S., Töre, C., Ortego, P.

Publikováno v: JRC Petten: AMES Report n.17, EUR 21771 EN, 200563 Seiten

The REDOS project aims to improve reactor dosimetry for radiation embrittlement monitoring of the reactor pressure vessel (RPV) steels. Benchmarking, as well as combined experimental and computational techniques, have been used. Specific objectives w

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=od______4577::6f74d5c28dc08bee96dec14b37e6f0be
https://www.hzdr.de/publications/Publ-8019-2

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Reactor Dosimetry: Accurate Determination and Benchmarking of Radiation Field Parameters, relevant for Pressure Vessel Monitoring (REDOS)

Autor: Ballesteros, A., Garcia, G., Böhmer, B., OMera, B., Keresztúri, A., Ilieva, K., Acosta, B., Smutný, V., Polke, E., Zaritsky, S., Ortego, P.

Publikováno v: FISA-2003-Symposium on EU Research in Reactor Safety, 10-13 November 2003, Luxembourg

Radiation embrittlement of reactor pressure vessel (RPV) steels is a degradation mechanism that requires crucial consideration for the safe operation of aged nuclear power plants. Plant life management needs a reliable estimation of radiation field p

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::c364654a3402ab19b572f9985111e357
https://www.hzdr.de/publications/Publ-5892-7

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Balakovo-3 Ex-vessel Exercise: Analysis of Calculation Results Intercomparison and Comparison with Reference Data

Autor: Borodkin, G., Böhmer, B., Konheiser, J., Manturov, G., Polke, E., Brodkin, E., Jegorov, A., Zaritsky, S.

Publikováno v: 11th International Symposium on Reactor Dosimetry, August 18-23, 2002 in Brussels, Belgium, Proceedings by World Scientific Publ., ISBN 981-238-448-0, p. 665-673

Ex-vessel neutron dosimetry at NPP with VVER was used for validation of 3D absolute neutron fluence calculations. As second step of the VVER-1000 Balakovo-3 Ex-vessel Exercise, an analysis of calculational results has been performed. The reference ex

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::7fe3cfe296e64355065bd045a6049983
https://www.hzdr.de/publications/Publ-4277-7

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Verification of neutron transport calculations for nonstandard pressure vessel surveillance positions in the VVER-1000 Novovoronesh-5

Autor: Böhmer, B., Konheiser, J., Brodkin, E., Egorov, A., Vikhrov, V., Zaritsky, S., Polke, E.

Publikováno v: Jahrestagung Kerntechnik 2001, Dresden, 15.-17. Mai 2001, Proceedings pp. 37-42

Activation measurements results at non-standard surveillance positions of the VVER-1000 Novovoronesh-5 have been used to verify neutron fluence calculations for pe-ripheral reactor regions with large flux gradients. Fluence integrals and activities o

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::10d77df8b67ba6837da7947ac6ad80fc
https://www.hzdr.de/publications/Publ-3647-1

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