Preliminary report on the promise of accelerator-driven natural-uranium-fueled light-water-moderated breeding power reactors
A new concept for a power breeder reactor that consists of an accelerator-driven subcritical thermal fission system is proposed. In this system an accelerator provides a high-energy proton beam which interacts with a heavy-element target to produce, via spallation reactions, an intense source of neutrons. This source then drives a natural-uranium-fueled, light-water-moderated and -cooled subcritical blanket which both breeds new fuel and generates heat that can be converted to electrical power. The report given presents a general layout of the resulting Accelerator Driven Light Water Reactor (ADLWR), evaluates its performance, discusses its fuel cycle characteristics, and identifies the potential contributions to the nuclear energy economy this type of power reactor might make. A light-water thermal fission system is found to provide an attractive feature when designed to be source-driven. The equilibrium fissile fuel content that gives the highest energy multiplication is approximately equal to the content of /sup 235/U in natural uranium. Consequently, natural-uranium-fueled ADLWRs that are designed to have the highest energy generation per source neutron are also fuel-self-sufficient; that is, their fissile fuel content remains constant with burnup. This feature allows the development of a nuclear energy system that is based on the most highly developed fission technology available (the light water reactor technology) and yet has a simple and safe fuel cycle. ADLWRs will breed on natural uranium, have no doubling time limitation, and be free from the need for uranium enrichment or for the separation of plutonium. It appears that ADLWRs could also be efficiently operated with thorium fuel cycles and with denatured fuel cycles.
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 5118376
- Report Number(s):
- ORNL/TM-6138; TRN: 78-008583
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
ACCELERATOR BREEDERS
FEASIBILITY STUDIES
BREEDER REACTORS
FISSILE MATERIALS
BREEDING
BREEDING BLANKETS
FUEL CYCLE
OPERATION
PROTON BEAMS
SAFETY
BEAMS
FISSIONABLE MATERIALS
NUCLEAR FUEL CONVERSION
NUCLEON BEAMS
PARTICLE BEAMS
REACTOR COMPONENTS
REACTORS
430100* - Particle Accelerators- Design
Development
& Operation
050500 - Nuclear Fuels- Uranium Enrichment
210500 - Power Reactors
Breeding