Sodium-cooled fast reactor core designs for transmutation of MHR spent fuel
Creators
- 1. Korea Atomic Energy Research Inst., 150 Duckjin-dong, Yuseong-Gu, Daejon, 305-600 (Korea, Republic of)
- 2. Ulsan National Inst. of Science and Technology (Korea, Republic of)
- 3. LOGOS Technologies (United States)
Description
In this paper, the core design analyses of sodium cooled fast reactors (SFR) are performed for the effective transmutation of the DB (Deep Burn)-MHR (Modular Helium Reactor). In this concept, the spent fuels of DB-MHR are transmuted in SFRs with a closed fuel cycle after TRUs from LWR are first incinerated in a DB-MHR. We introduced two different type SFR core designs for this purpose, and evaluated their core performance parameters including the safety-related parameters. In particular, the cores are designed to have lower transmutation rate relatively to our previous work so as to make the fuel characteristics more feasible. The first type cores which consist of two enrichment regions are typical homogeneous annular cores and they rate 900 MWt power. On the other hand, the second type cores which consist of a central non-fuel region and a single enrichment fuel region rate relatively higher power of 1500 MWt. For these cores, the moderator rods (YH1.8) are used to achieve less positive sodium void worth and the more negative Doppler coefficient because the loading of DB-MHR spent fuel leads to the degradation of these safety parameters. The analysis results show that these cores have low sodium void worth and negative reactivity coefficients except for the one related with the coolant expansion but the coolant expansion reactivity coefficient is within the typical range of the typical SFR cores. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park (United States)
- ISBN
- 978-89448-081-2
- Imprint Title
- Proceedings of the 2010 International Congress on Advances in Nuclear Power Plants - ICAPP '10
- Imprint Pagination
- 2284 p.
- Journal Page Range
- p. 569-574
Conference
- Title
- 2010 International Congress on Advances in Nuclear Power Plants
- Acronym
- ICAPP '10
- Dates
- 13-17 Jun 2010
- Place
- San Diego, CA (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 42097780
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; DESIGN; DOPPLER COEFFICIENT; FAST REACTORS; FUEL CYCLE; HELIUM COOLED REACTORS; REACTOR CORES; SAFETY ANALYSIS; SODIUM COOLED REACTORS; SPENT FUELS; TRANSURANIUM ELEMENTS
- Descriptors DEC
- ELEMENTS; ENERGY SOURCES; EPITHERMAL REACTORS; FUELS; GAS COOLED REACTORS; LIQUID METAL COOLED REACTORS; MATERIALS; NUCLEAR FUELS; REACTIVITY COEFFICIENTS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS
Optional Information
- Notes
- 10 refs.