Fast Reactors and Accelerator Driven Systems Knowledge Base

Working Materials of the Technical Working Group on Fast Reactors

Consultancy on “Implementing Thorium in Nuclear Reactor Fuel Cycles: Potential Benefits and Challenges”
, VIC, Vienna, Austria, 9–11 December 2003
report nr.: TWGFR/115
IAEA-03CT13095
 

The objective of this consultancy (CS) was to bring together experts from the MS to discuss R&D developments in the study of thorium fuel cycles and to identify MS needs in support of national activities in this area. The CS was also meant to define an appropriate IAEA response to these needs, e.g., recommend topics for information exchange and collaborative R&D activities to be implemented in a planned CRP. Presentations were made on past thorium-fuel-cycle activities at IAEA, and on R&D activities in Canada, India and the Russian Federation. Following these presentations and further discussions on topics of importance in thoriumbased fuel cycles, the CS arrived at a proposal for a new CRP entitled “The Comparative Assessment of the Fuel-Cycle Aspects of Various Thorium-Based Reactor Concepts”. The CRP should be based on a unified systematic approach for a comparative assessment of the various designs for utilizing thorium fuel, and their potential benefits as compared to uranium-plutonium fuelled systems. The CS recommended a list of fuel-cycle performance parameters to be considered in the CRP for the above purpose. Finally, the CS proposed a plan of action for the initiation of the CRP by the Scientific Secretary.

Presentations
IAEA Activities in the Area of Thorium Based Nuclear Fuel cycles
  Young-In Kim (IAEA)
Direct Self-Recycle Thorium Fuel Cycle in the Advanced CANDU Reactor
  G.R. Dyck, P.G. Boczar, B. Rouben (AECL)
Implementation of Thorium Fuel Cycle in Indian Nuclear Programme
  P.D. Krishnani and R. Srivenkatesan (BARC)
Main Investigation Directions of Implementing Thorium in Nuclear Reactor Fuel Cycles
  V. Dekoussar, A. Kalashnikov (IPPE)
Fuel Cycle Performance Indicies in a High-Converting LWR Core Design with Once-Through Thorium Fuel Cycle
  Myung-Hyun Kim, Kwan-Hee Kim (Kyung Hee Univ.), Young-il Kim (KAERI)
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