Výsledky vyhledávání - "Zaritsky, S."

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Erhöhung der Zuverlässigkeit der Bestimmung der Neutronenbelastung von WWER-Reaktorkomponenten zwecks Ableitung von Vorschlägen für eine sicherere Betriebsführung von WWER-Reaktoren

Autor: Gorbunov, V. P., Tsiboulia, A. M., Borodkin, G. I., Zaritsky, S. M., Böhmer, Bertram, Manturov, G. N., Brodkin, E. B.

Publikováno v: Forschungszentrum Rossendorf; FZR-220, Juli 1998

The results of a project sponsored by the German Bundesministerium fuer Bildung, Wissenschaft, Forschung und Technologie are presented. The Project aimed to improve the safety against embrittlement of VVER-1000 type reactors by a more reliable and ac

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Akademický článek

Neutron fluence calculations for embrittlement surveillance specimens in VVER-1000

Autor: Konheiser, J. ^{a, ⁎}, Mittag, S. ^a, Zaritsky, S. ^b

Publikováno v: In Annals of Nuclear Energy 2009 36(8):1235-1241

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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

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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

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https://www.hzdr.de/publications/Publ-3647-1

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CONTRIBUTION OF GAMMA IRRADIATION TO MATERIAL DAMAGE AT VVER PRESSURE VESSELS

Autor: Brodkin, E., Egorov, A., Zaritsky, S., Böhmer, B.

Publikováno v: Jahrestagung Kerntechnik 2000, Bonn, 23.-25.Mai 2000, Proceedings pp. 597-600

Neutron and gamma ray spectra at the VVER reactor pressure vessel (RPV) were calculated using the discrete ordinates method. Assessments of dpa and freely-migrating defect (FMD) rates based on these spectra are presented. It was found that the gamma

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::1bde6b5012d322d1bd96b4ad40a854ab
https://www.hzdr.de/publications/Publ-3037-1

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Erhöhung der Zuverlässigkeit der Bestimmung der Neutronenbelastung von WWER-Reaktorkomponenten zwecks Ableitung von Vorschlägen für eine sicherere Betriebsführung von WWER-Reaktoren

Autor: Böhmer, B., Borodkin, G. I., Brodkin, E. B., Gorbunov, V. P., Manturov, G. N., Tsiboulia, A. M., Zaritsky, S. M.

Publikováno v: Forschungszentrum Rossendorf; FZR-220, Juli 1998

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::b1f5fa9c76329ba1a95bae537b6dc593
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Experimental and Calculation Characterization of Irradiation Facility KORPUS

Autor: Markina, N. V., Riasanov, D. K., Tellin, A. I., Lichadeev, V. V., Pavlov, V. V., Tsikanov, V. A., Brodkin, E. B., Egorov, A. L., Zaritsky, S. M., Bars, B., Stephan, I., Voorbrack, W., Nolthenius, H., Ait Abderrahim, H.

Publikováno v: Proc. 9th International Symposium on Reactor Dosimetry, Prague, Sept. 2-6, 1996

The preliminary results of the activation measurements and calculations in the different points of the irradiation facility KORPUS are shortly described and analyzed. The tasks of these investigations are the dosimetry characterization of the facilit

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=od______4577::42258550e1486566762d96b544e631d0
https://www.hzdr.de/publications/Publ-1734-1

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