Estimation of material degradation of VVER-1000 baffle
- 1. Research Center Rez Ltd., 250 68 Husinec-Rez 130 (Czech Republic)
- 2. Department of Nuclear Reactors, FNSFE, CTU Prague, V Holesovickach 2, Prague 8 (Czech Republic)
Description
This article aims to show first steps towards deeper analysis of the baffle degradation process and to demonstrate the possibilities of precise calculation and measurements on the VVER-1000 mock-up in LR-0 reactor. Displacement per atom and gamma heating calculations were done with MCNP6 model of LR-0 VVER-1000 mock-up.The MCNP calculations provide data which are impossible to measure, such as deposited energy of particles. Completing this data with thermo-hydraulic computation, it is possible to assess void swelling. The same calculation has also be done with the TORT code. MCNP results for dpa and gamma heating in selected part of baffle are in an agreement with TORT results. Both distributions are comparable. Maximum dpa integrated over a year was estimated using MCNP as 2.5 and by TORT as 1.5 dpa. Maximum gamma heating in MCNP calculation is 4 W/cm3 compared with 8 W/cm3 in case of TORT. Used methods for absolute dpa and gamma heating estimation via MCNP calculations seems to be applicable for the VVER-1000 reactor. The reason for a variance in the absolute values are due to the slight differences in the 2 codes for nuclear parameters, geometry definition of computational models and by scaling process in MCNP
Availability note (English)
Available from doi: http://dx.doi.org/10.1051/epjconf/201715307019Additional details
Identifiers
Publishing Information
- Publisher
- EDP Sciences
- Imprint Place
- Les Ulis (France)
- Imprint Title
- EPJ Web of Conferences, Proceedings of the 13. international conference on radiation shielding and 19. topical meeting of the radiation protection and shielding division of the American Nuclear Society - 2016
- Imprint Pagination
- v. 153 [1590 p.]
- Journal Page Range
- p. 07019.p.1-07019.p.6
Conference
- Title
- 13. international conference on radiation shielding; RPSD-2016: 19. topical meeting of the radiation protection and shielding division of the American Nuclear Society
- Acronym
- ICRS-13
- Dates
- 3-6 Oct 2016
- Place
- Paris (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 51050035
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ATOMIC DISPLACEMENTS; BAFFLES; COMPUTERIZED SIMULATION; M CODES; RADIATION HEATING; REACTOR CORES; T CODES; VALIDATION; WWER TYPE REACTORS
- Descriptors DEC
- COMPUTER CODES; CONTROL EQUIPMENT; ENRICHED URANIUM REACTORS; EQUIPMENT; FLOW REGULATORS; HEATING; PHYSICAL RADIATION EFFECTS; POWER REACTORS; PWR TYPE REACTORS; RADIATION EFFECTS; REACTOR COMPONENTS; REACTORS; SIMULATION; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 13 refs.; This record replaces 51039588