Evaluation of U-Zr Hydride Fuel for a Thorium Fuel Cycle in an RTR Concept

  • Lee, Kyung-Taek (Korea Advanced Institute of Science and Technology, Department of Nuclear Engineering) ;
  • Cho, Nam-Zin (Korea Advanced Institute of Science and Technology, Department of Nuclear Engineering)
  • 발행 : 1998.05.01

초록

In this paper, we performed a design study of a thorium fueled reactor according to the design concept of the Radkowsky Thorium Reactor (RTR) and evaluated its overall performance. To enhance its performance and alleviate its problems, we introduced a new metallic uranium fuel, uranium-zirconium hydride (U-Zr $H_{1.6}$), as a seed fuel. For comparison, typical ABB/CE-type PWR based on SYSTBM 80+ and standard RTR-type thorium reactor were also studied. From the results of performance analysis, we could ascertain advantages of RTR-type thorium fueled reactor in proliferation resistance, fuel cycle economics, and back-end fuel cycle. Also, we found that enhancement of proliferation resistance and safer operating conditions may be achieved by using the U-Zr $H_{l.6}$ fuel in the seed region without additional penalties in comparison with the standard RTR's U-Zr fuelr fuelel

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