Radiation transport out from the reactor core: to decouple or not to decouple
Description
In the framework of the extension of the lifetime of currently operating reactors as well as of issues connected to decommissioning, accurate calculations of neutron and gamma responses outside the reactor core are increasingly being sought. Recently Monte Carlo calculations have been extended to provide a deep penetration capability incorporated within the eigenvalue calculation. This allows, in principle, neutron and gamma ray responses quite far outside the fissile region to be calculated within the same source-iteration scheme employed to define the neutronic responses in the fissile zone. In this paper, the new algorithm is compared to the classic decoupled approach - an eigenvalue calculation followed by a fixed source one - with the point of decoupling chosen as the fission sites. Two contrasting sample problems are discussed: a small fast research reactor and a large GEN-III Pressurized Water Reactor. The latter problem highlights the role of super-histories in maintaining the fundamental mode. (authors)
Availability note (English)
Available from doi: http://dx.doi.org/10.1051/epjconf/201715305007Additional 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. 05007.p.1-05007.p.12
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
- 51049963
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; MONTE CARLO METHOD; NEUTRON FLUX; NEUTRON LEAKAGE; PWR TYPE REACTORS; SPATIAL DISTRIBUTION; TAPIRO REACTOR
- Descriptors DEC
- CALCULATION METHODS; DISTRIBUTION; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; FAST REACTORS; POWER REACTORS; RADIATION FLUX; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SIMULATION; TEST FACILITIES; TEST REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 13 refs.; This record replaces 51039516