Neutron spectra in thorium and depleted uranium-plutonium-loaded light water reactors
The technical feasibility of using plutonium mixed with natural uranium in one-third of the cores of light water reactors (LWRs) has been sufficiently demonstrated. A number of reactors in Europe are currently operated with one-third mixed-oxide cores. If the option of burning excess plutonium in conventional LWR reactors in this country is selected, it has been estimated that the long-term disposition of the excess plutonium would take many decades. This time can be significantly reduced if the plutonium is burned in a fast breeder reactor. However, in the present economic and political climate, such an approach is difficult to implement. On the other hand, if the neutron spectrum in an LWR core is hardened, the well-developed and well-understood LWR can accomplish the goal of effectively burning excess plutonium to convert to proliferation-resistive fuel such as {sup 233}U. The authors present some fundamental characteristics of thorium and depleted uranium-plutonium-fueled LWRs. High fuel burnup levels can be achieved by tightening the lattice of an LWR loaded with thorium and depleted uranium and plutonium (nitride or oxide) and increasing the plutonium content. The neutron spectrum in such a reactor is very hard and tends to approach that of a Na-cooled fast reactor. Instead of Zircaloy, stainless steel can be used as fuel cladding and structural material since it has a low fast neutron capture cross section. Supercritical steam, generated at high pressures, can be used as coolant. If the cladding and structural materials used in this reactor can withstand corrosion in water under high-irradiation conditions, high conversion ratios of thermal heat to electricity will be possible.
- Research Organization:
- Brookhaven National Lab., Upton, NY (US)
- OSTI ID:
- 20005833
- Journal Information:
- Transactions of the American Nuclear Society, Vol. 81; Conference: American Nuclear Society 1999 Winter Meeting, Long Beach, CA (US), 11/14/1999--11/18/1999; Other Information: PBD: 1999; ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
Similar Records
Transuranic Waste Burning Potential of Thorium Fuel in a Fast Reactor - 12423
Analysis of Synergistic Fuel Cycle Options with Thorium and Heavy Water Reactors