Design of small-size ultra-long cycle fast reactor with PWR spent fuel - KF149
Creators
- 1. Ulsan National Institute of Science and Technology, UNIST-gil 50, Eonyang-eup, Ulju-gun, Ulsan, 689-798 (Korea, Republic of)
Description
A new design of small-size (100 MWe) Ultra-long Cycle Fast Reactor (UCFR-100) has been developed with the light water reactor (LWR) spent fuel loaded in the upper region of the core as a blanket material for breeding. The low enriched uranium (LEU) in the bottom region plays a role of igniter of the core burning and the active burning region of the core moves upward at a speed of 1 cm/year. It has been confirmed that the full power operation for 60 years without refueling is feasible in the aspect of neutronics by the core depletion analysis using McCARD Monte Carlo depletion code. The core performance characteristics of UCFR-100 have been evaluated in terms of axial/radial power distribution, reactivity feedback coefficients, and the average discharge burnup. (authors)
Additional details
Publishing Information
- Publisher
- Curran Associates Inc.
- Imprint Place
- Red Hook, NY (United States)
- ISBN
- 978-1-63266-038-1
- Imprint Pagination
- 7 p.
Conference
- Title
- 2013 International Congress on Advances in Nuclear Power Plants; 28. KIF/KNS annual conference
- Acronym
- ICAPP'13
- Dates
- 14-18 Apr 2013
- Place
- Jeju Island (Korea, Republic of)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 54009877
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BREEDING; BURNUP; ENRICHED URANIUM; FAST REACTORS; MONTE CARLO METHOD; NEUTRON TRANSPORT; PERFORMANCE; POWER DISTRIBUTION; PWR TYPE REACTORS; REACTIVITY COEFFICIENTS; REACTOR DESIGN; REACTOR OPERATION; SPENT FUELS
- Descriptors DEC
- ACTINIDES; CALCULATION METHODS; DESIGN; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; FUELS; ISOTOPE ENRICHED MATERIALS; MATERIALS; METALS; NEUTRAL-PARTICLE TRANSPORT; NUCLEAR FUEL CONVERSION; NUCLEAR FUELS; OPERATION; POWER REACTORS; RADIATION TRANSPORT; REACTOR LIFE CYCLE; REACTOR MATERIALS; REACTORS; THERMAL REACTORS; URANIUM; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 30 refs.; Available from Curran Associates, Inc., 57 Morehouse Lane, Red Hook, NY 12571 (US)