Fast neutron fluence reduction strategy at the pressure vessel for a pressurized water reactor lifetime extension
Creators
- 1. Hanyang University, Department of Nuclear Engineering, 17 Haengdang, Sungdong, Seoul 133-791 (Korea, Republic of)
- 2. Kepco Nuclear Fuel Co. Ltd., Nuclear Design Group, 150 Dukjin, Yusong Taejon 305-353 (Korea, Republic of)
Description
The feasibility of nuclear power plant lifetime extension was examined by reducing the fast neutron fluence at the RPV and relieving irradiation embrittlements of materials, and thus ensuring enough structural integrity to last beyond the design lifetime. Two fluence reduction options, peripheral assembly replacements and additional shield installation in the outer core structures, were applied to the Kori Unit 1 reactor, and fluence reduction effect was carefully analyzed. For an accurate estimate of the neutron fluence at the RPV and a reasonable description of the modified peripheral assemblies, a full-scope explicit modeling of a Monte Carlo simulation was employed in ail calculations throughout this study. The Kori Unit 1 cycle 16 core was modeled on a three dimensional representation by using MCNP4B code, and the fluence distribution was estimated at inner wall beltline around the circumferential weld of the RPV. On the basis of fracture toughness requirements of the RPV, the two modified cases were predicted to have additional life of 7-10 EFPYs. Throughout the core nuclear characteristics analyses, it was confirmed that the critical peaking factors for safe reactor operation were satisfied with the design limits
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- Jackson Hole, Wyoming (United States)
- Imprint Pagination
- 6 p.
Conference
- Title
- International Conference on Future Nuclear Systems - Nuclear Technology - Bridging the Millennia
- Acronym
- Global'99
- Dates
- 29 Aug - 3 Sep 1999
- Place
- Las Vegas, NV (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 53059415
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; DESIGN; EMBRITTLEMENT; FAST NEUTRONS; FRACTURE PROPERTIES; IRRADIATION; KORI-1 REACTOR; LIFETIME EXTENSION; MATERIALS; MONTE CARLO METHOD; NEUTRON FLUENCE; NUCLEAR CORES; NUCLEAR POWER PLANTS; PRESSURE VESSELS; REACTOR OPERATION; SHIELDS; THREE-DIMENSIONAL CALCULATIONS; WELDED JOINTS
- Descriptors DEC
- BARYONS; CALCULATION METHODS; CONTAINERS; ELEMENTARY PARTICLES; ENRICHED URANIUM REACTORS; FERMIONS; HADRONS; JOINTS; LIFETIME; MECHANICAL PROPERTIES; NEUTRONS; NUCLEAR FACILITIES; NUCLEONS; OPERATION; POWER PLANTS; POWER REACTORS; PWR TYPE REACTORS; REACTOR LIFE CYCLE; REACTORS; SERVICE LIFE; SIMULATION; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 13 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)