A Simulation of Rod Ejection Accident in an Advanced Small PWR Core without Soluble Boron
Creators
- 1. Department of Nuclear Engineering, Kyung Hee University: 1732 Deokyoung-daero, Giheung-gu, Yongin, Gyeonggido, 446-701 (Korea, Republic of)
Description
The soluble boron is used to control the long-term excess reactivity in commercial PWRs but the use of soluble boron has disadvantages such as complications of the reactor coolant system and generation of the liquid wastes. Therefore, there have been lots of interests in designing PWR reactor without soluble boron. Recently, we have designed new small 50 MWe PWR core having no soluble boron for long-term reactivity control. In the core, the excess reactivity is controlled by using the control rods and the advanced particle type burnable poisons over the cycle. The one of the most important issues for the boron-free core is to check if the core is safe under the rod ejection accidents because the reactor is operated with insertion of the control rods. The objective of this work is to give the detailed analysis results of the rod ejection accidents for the advanced small PWR core were analyzed. (authors)
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 115
- Journal Page Range
- p. 1331-1333
- ISSN
- 0003-018X
Conference
- Title
- 2016 ANS Winter Meeting and Nuclear Technology Expo
- Dates
- 6-10 Nov 2016
- Place
- Las Vegas, NV (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 52083218
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BORON; BURNABLE POISONS; COMPUTERIZED SIMULATION; CONTROL ELEMENTS; LIQUID WASTES; PWR TYPE REACTORS; REACTIVITY; REACTOR COOLING SYSTEMS; REACTOR DESIGN; ROD EJECTION ACCIDENTS
- Descriptors DEC
- ACCIDENTS; COOLING SYSTEMS; DESIGN; ELEMENTS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; MATERIALS; NEUTRON ABSORBERS; NUCLEAR POISONS; POWER REACTORS; REACTIVITY-INITIATED ACCIDENTS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR LIFE CYCLE; REACTOR MATERIALS; REACTORS; SEMIMETALS; SIMULATION; THERMAL REACTORS; WASTES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 4 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)