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Title: The Behavior of ThO{sub 2}-Based Fuel Rods During Normal Operation and Transient Events in LWRs

Journal Article · · Nuclear Technology
OSTI ID:20840210
 [1];  [2];  [1];  [2];  [2];  [2];  [1]
  1. Massachusetts Institute of Technology (United States)
  2. Idaho National Engineering and Environmental Laboratory (United States)

The thermal, mechanical, and chemical behavior of both thorium and uranium dioxide (ThO{sub 2}-UO{sub 2}) and thorium and plutonium dioxide (ThO{sub 2}-PuO{sub 2})-based fuels during in-service and hypothetical accident conditions in light water reactors (LWRs) is described. These fuels offer the possibility for increased proliferation resistance and a reduction in the stockpile of weapons-grade and reactor-grade PuO{sub 2} as well as being a more stable waste form. The behavior is described for three different designs of ThO{sub 2}-based fuels: a homogeneous mixture of ThO{sub 2}-UO{sub 2}, a microheterogeneous arrangement of the ThO{sub 2} and UO{sub 2}, and a homogeneous mixture of ThO{sub 2}-PuO{sub 2}. The behavior was calculated with widely known LWR analysis tools extended for ThO{sub 2}-based fuels: (a) MATPRO for calculating material properties, (b) FRAPCON-3 for calculating in-service fuel temperature and fission-gas release, (c) VIPRE-01 for calculating the possibility for departure from nucleate boiling, (d) HEATING7 for calculating in-service two-dimensional temperature distributions in microheterogeneous fuel, (e) SCDAP/RELAP5-3D for calculating the transient reactor system behavior and fuel behavior during loss-of-coolant accidents, and (f) FRAP-T6 for calculating the vulnerability of the cladding to cracking due to swelling of the fuel during hypothetical reactivity-initiated accidents.The analytical tools accounted for the following differences in ThO{sub 2}-based fuels relative to 100% UO{sub 2} fuel: (a) higher thermal conductivity, lower density and volumetric heat capacity, less thermal expansion, and higher melting point; (b) higher fission-gas production for {sup 233}U fission than {sup 235}U fission, but a lower gas diffusion coefficient in the ThO{sub 2} than in the UO{sub 2}; (c) less plutonium accumulation at the rim of the fuel pellets; (d) greater decay heat; (e) microheterogeneous arrangement of fuel; and (f) more-negative moderator temperature and Doppler coefficients and a smaller delayed-neutron fraction. The newly developed models for ThO{sub 2} were checked against data from the light water breeder reactor program. Calculations by these analytical tools indicate that the in-service and transient performance of homogeneous ThO{sub 2}-UO{sub 2}-based fuels with respect to safety is generally equal to or better than that of 100% UO{sub 2} fuel. The in-service and transient temperatures in the most promising neutronic design of microheterogeneous ThO{sub 2}-UO{sub 2}-based fuel are greater than the temperatures in 100% UO{sub 2} fuel but are still within normal LWR safety limits. The reactor kinetics parameters for ThO{sub 2}-PuO{sub 2}-based fuel cause a higher transient reactor power for some postulated accidents, but in general, the margin of safety for ThO{sub 2}-PuO{sub 2} fuels is equal to or greater than that in 100% UO{sub 2} fuels.

OSTI ID:
20840210
Journal Information:
Nuclear Technology, Vol. 147, Issue 1; Other Information: Copyright (c) 2006 American Nuclear Society (ANS), United States, All rights reserved. http://epubs.ans.org/; Country of input: International Atomic Energy Agency (IAEA); ISSN 0029-5450
Country of Publication:
United States
Language:
English