Published 2011 | Version v1
Miscellaneous

Comparison of attenuation coefficients for VVER-440 and VVER-1000 pressure vessels

Description

The paper summarizes the attenuation coefficient of the neutron fluence with E > 0.5 MeV through a reactor pressure vessel for vodo-vodyanoi energetichesky reactor (VVER) reactor types measured and/or calculated for mock-up experiments, as well as for operated nuclear power plant (NPP) units. The attenuation coefficient is possible to evaluate directly only by using the retro-dosimetry, based on a combination of the measured activities from the weld sample and concurrent ex-vessel measurement. The available neutron fluence attenuation coefficients (E > 0.5 MeV), calculated and measured at a mock-up experiment simulating the VVER-440-unit conditions, vary from 3.5 to 6.15. A similar situation is used for the calculations and mock-up experiment measurements for the VVER-1000 RPV, where the attenuation coefficient of the neutron fluence varies from 5.99 to 8.85. Because of the difference in calculations for the real units and the mock-up experiments, the necessity to design and perform calculation benchmarks both for VVER-440 and VVER-1000 would be meaningful if the calculation model is designed adequately to a given unit. (authors)

Availability note (English)

Available from the INIS Liaison Officer for France, see the INIS contacts section of the INIS website for current contact and E-mail addresses: http://www.iaea.org/INIS/contacts/

Additional details

Publishing Information

Imprint Pagination
9 p.
Report number
INIS-US--13-ISRD-14-os1p-4

Conference

Title
14. International Symposium on Reactor Dosimetry
Acronym
ISRD-14
Dates
22-27 May 2011
Place
Bretton Woods, NH (United States)

Optional Information

Notes
29 refs.