Assessment of Shutdown Margin Requirements for High Conversion BWR with Th-U233 Fuel - 14402
Creators
- 1. Department of Nuclear Engineering, Ben-Gurion University of the Negev, POB 653, Beer Sheva 84105 (Israel)
- 2. NRCN - Nuclear Research Center Negev, POB 9001, Beer Sheva 84190 (Israel)
- 3. Faculty of Mechanical Engineering, Technion - Israel Institute of Technology, Technion city, 32000 Haifa (Israel)
Description
A number of reactivity control system design options are explored in order to satisfy shutdown margin (SDM) requirements in a high conversion BWRs operating in Th-233U fuel cycle (Th-RBWR). The studied core has an axially heterogeneous fuel assembly structure with a single fissile zone located between two fertile blanket zones. The utilization of an originally suggested RBWR Y-shape control rod in Th-RBWR is shown to be insufficient for maintaining adequate SDM to balance the high negative reactivity feedbacks, while maintaining fuel breeding potential, core power rating, and minimum Critical Power Ratio (CPR). Implementation of alternative reactivity control materials, reducing axial leakage through non-uniform enrichment distribution, use of burnable poisons, reducing number of pins as well as increasing pin diameter are shown to be incapable of meeting the SDM requirements. Instead, an alternative assembly design based on Rod Cluster Control Assembly with absorber rods was investigated. This design matches the reference ABWR core power and has adequate shutdown margin. The study focused on the neutronic performance of the concept and was based on a single 3-dimensional fuel assembly model having reflective radial boundaries. The analyses were performed using BGCore code system, which consists of the MCNP code coupled with fuel depletion and thermo-hydraulic feedback modules. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park, IL (United States)
- ISBN
- 978-0-89448-776-7
- Imprint Pagination
- 10 p.
Conference
- Title
- International Congress on Advances in Nuclear Power Plants
- Acronym
- ICAPP 2014
- Dates
- 6-9 Apr 2014
- Place
- Charlotte, NC (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 54022700
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BREEDING; BURNABLE POISONS; BWR TYPE REACTORS; CONTROL ELEMENTS; CONTROL SYSTEMS; FUEL ASSEMBLIES; FUEL CYCLE; HYDRAULICS; NEUTRON TRANSPORT; NUCLEAR FUELS; PERFORMANCE; REACTIVITY COEFFICIENTS; REACTOR DESIGN; THREE-DIMENSIONAL CALCULATIONS; URANIUM 233
- Descriptors DEC
- ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; DESIGN; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EVEN-ODD NUCLEI; FLUID MECHANICS; FUELS; HEAVY ION DECAY RADIOISOTOPES; HEAVY NUCLEI; ISOTOPES; MATERIALS; MECHANICS; NEON 24 DECAY RADIOISOTOPES; NEUTRAL-PARTICLE TRANSPORT; NEUTRON ABSORBERS; NUCLEAR FUEL CONVERSION; NUCLEAR POISONS; NUCLEI; POWER REACTORS; RADIATION TRANSPORT; RADIOISOTOPES; REACTOR COMPONENTS; REACTOR LIFE CYCLE; REACTOR MATERIALS; REACTORS; SPONTANEOUS FISSION RADIOISOTOPES; THERMAL REACTORS; URANIUM ISOTOPES; WATER COOLED REACTORS; WATER MODERATED REACTORS; YEARS LIVING RADIOISOTOPES
Optional Information
- Notes
- 21 refs.; Available on CD-ROM from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)