Neutronic design of advanced sodium cooled TRU burner cores using moderator rods and absorber region
Creators
- 1. Kyung Hee Univ., Dept. of Nuclear Engineering, Giheung-gu, Yong-in, Gyeong-gi-do (Korea, Republic of)
Description
In this paper, 400MWe sodium cooled fast reactor cores having high TRU burning rate are designed and neutronically analyzed. In particular, new fuel assembly concept having a thick duct is used in central region of the cores to achieve the power flattening under a single TRU contents in charging fuel by reducing fuel volume fraction in the central core region and the use of this new fuel assembly also increases TRU burning rate by reducing conversion ratio. To further increase TRU burning rate, B4C absorber regions are considered to be placed in the axially central parts of all fuel rods and their combined effects with 12 ZrH1.8 moderator rods per one fuel assembly on the core performances are analyzed in detail. The results show that the use of B4C absorber in axially central region of core effectively reduces the sodium void worth and significantly increases TRU burning rate and that its combined use with ZrH1.8 moderator rods leads to further improvements of core performances including TRU burning rate, sodium void worth, and Doppler coefficient. (author)
Additional details
Publishing Information
- Publisher
- Canadian Nuclear Society
- Imprint Place
- Toronto, Ontario (Canada)
- ISBN
- 978-1-926773-16-2
- Imprint Title
- PBNC 2014 : 19th Pacific Basin Nuclear Conference; 38th Annual Student Conference of the Canadian Nuclear Society and Canadian Nuclear Association
- Imprint Pagination
- 270 Megabytes
- Journal Page Range
- [10 p.]
Conference
- Title
- 19. Pacific Basin Nuclear Conference; 38. Annual Student Conference of the Canadian Nuclear Society and Canadian Nuclear Association
- Dates
- 24-28 Aug 2014
- Place
- Vancouver, British Columbia (Canada)
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 49016173
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- FUEL ASSEMBLIES; FUEL RODS; NEUTRON ABSORBERS; NEUTRON TRANSPORT; REACTOR CORES; SODIUM COOLED REACTORS
- Descriptors DEC
- FUEL ELEMENTS; LIQUID METAL COOLED REACTORS; NEUTRAL-PARTICLE TRANSPORT; RADIATION TRANSPORT; REACTOR COMPONENTS; REACTORS
Optional Information
- Notes
- Paper PBNC2014-060. 15 refs., 5 tabs., 5 figs.