Fusion--fission breeder its potential in a fuel-starved thermal reactor economy
Conference
·
OSTI ID:4308299
ABS>From international meeting on the technology of controlled thermonuclear iusion experiments and the engineering aspects of fusion reactors; Austin, Texas, USA (20 Nov 1972). In technology of controlled thermonuclear fusion experiments and the engineering aspects of fusion reactors. Although eventual development of a safe commercial liquid-metal fast breeder reactor (LMFBR) appears likely, the possibility remains that its development may be delayed by a number of factors: technical difficulties, cost overruns, environmental resistance, etc. While estimates of the availability of uranium ore vary widely, enriched uranium or plutonium requirements can be calculated with considerably more accuracy. In the early 1980s the AEC's uranium-enrichment plants will reach stretched capacity. New gaseous diffusion or centrifuge plants will have to be constructed at great cost to meet the fuel needs of the thermal reactor economy. Beyond the 1980s though, the supply of fissionable fuel will depend critically on the commercial viability of the LMFBR. This paper discusses one technical approach that couid help meet the critical fuel need if the LMFBR is delayed and could significantly advance the development of the fusion reactor at the same time. (auth)
- Research Organization:
- Univ. of Texas, Austin; Texas Univ., Austin (USA)
- NSA Number:
- NSA-29-030970
- OSTI ID:
- 4308299
- Report Number(s):
- CONF-721111--
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
Similar Records
Neutron and gamma heating rates in fusion-reactor blankets
Fusion--fission hybrids: a subcritical thermal fission lattice for a D--T fusion reactor
Cooling of controlled thermonuclear fusion reactors of toroidal configurations
Conference
·
Mon Apr 01 00:00:00 EDT 1974
·
OSTI ID:4322470
Fusion--fission hybrids: a subcritical thermal fission lattice for a D--T fusion reactor
Conference
·
Mon Apr 01 00:00:00 EDT 1974
·
OSTI ID:4327125
Cooling of controlled thermonuclear fusion reactors of toroidal configurations
Conference
·
Mon Apr 01 00:00:00 EDT 1974
·
OSTI ID:4306439