skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Molten-salt reactors for efficient nuclear fuel utilization without plutonium separation

Journal Article · · Nucl. Technol.; (United States)
OSTI ID:5688579

Molten-salt reactors (MSRs), because of the fluid nature of the fuel, appear to provide an attractive approach to efficient fuel utilization in the thorium-/sup 233/U cycle as well as a means for limiting the availability of plutonium and the general proliferation risks associated with nuclear power generation. High-enrichment /sup 233/U systems could, in principle, be operated with positive breeding gains to effectively eliminate plutonium as a nuclear fuel. However, such systems would be proliferation sensitive. Concept modifications (short of denaturing the uranium fuel) can be conceived to enhance the proliferation resistance of high-enrichment MSRs, but it is doubtful that sufficient enhancement could be achieved to make the systems suitable for deployment other than at secure sites. Denaturing the uranium in an MSR introduces some plutonium into the fuel cycle and generally degrades its breeding performance. Nevertheless, a denatured MSR with full-scale on-site fuel reprocessing appears to be capable of break-even breeding. In addition, the plutonium (most of which is consumed in situ) would be of poor quality and could never be isolated from all other undesirable nuclides. Thus, such systems would provide for efficient utilization of uranium resources in a proliferation-resistant environment while limiting the amount of plutonium (and transplutonium actinides) that would have to be handled as waste. The development of commercial MSRs by early in the 21st century appears to be technologically feasible.

Research Organization:
Oak Ridge National Lab., TN
OSTI ID:
5688579
Journal Information:
Nucl. Technol.; (United States), Vol. 46:1
Country of Publication:
United States
Language:
English