Conceptual design for a supercritical-water-cooled Candu
- AECL, Chalk River Laboratories, Chalk River, Ontario, Canada KOJ 1JO (Canada)
AECL has a program with the objective of examining Candu reactor concepts (Candu X) with enhanced passive safety and a 50% reduction in unit energy cost. The major cost reduction potential is provided by an increase in the coolant temperature into the supercritical regime, thereby increasing thermodynamic efficiency, without encountering the two-phase region and associated fuel dryout problems. The large reduction in water density yields a reduction in water inventory, and a corresponding reduction in coolant void reactivity. Supercritical water coolant also opens up the possibility of natural circulation primary flow provided that flow instabilities are avoided. Two stages of development for a supercritical-water-cooled Candu X have been identified based on the choice of material for fuel cladding. The Mark 1 concept is proposed to operate with a coolant core-mean temperature around the critical point (∼400 deg. C), as this is currently the limit for Zr-alloy cladding. For core mean temperatures near 500 deg. C (Mark 2), an advanced high temperature cladding, perhaps a ceramic, will be required. For both concepts, the temperature and pressure of the coolant will require a new fuel channel design.
- Research Organization:
- American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
- OSTI ID:
- 23142179
- Resource Relation:
- Conference: Global'99: International Conference on Future Nuclear Systems - Nuclear Technology - Bridging the Millennia, Las Vegas, NV (United States), 29 Aug - 3 Sep 1999; Other Information: Country of input: France; 8 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
ALLOYS
ATOMIC ENERGY OF CANADA LTD
CANDU TYPE REACTORS
CERAMICS
CLADDING
COOLANTS
DENSITY
DRYOUT
EFFICIENCY
FUEL CHANNELS
NATURAL CONVECTION
NUCLEAR FUELS
REACTIVITY
REACTOR DESIGN
REACTOR SAFETY
THERMODYNAMICS
WATER COOLED REACTORS