Published December 2013 | Version v1
Journal article

Comparative analysis of thorium and uranium fuel for transuranic recycle in a sodium cooled Fast Reactor

  • 1. Politecnico di Milano, Milan (Italy)
  • 2. Argonne National Laboratory, Argonne, IL (United States)
  • 3. Westinghouse Electric Company LLC, Cranberry Township, Pittsburgh, PA (United States)
  • 4. Idaho National Laboratory, Idaho Falls, ID (United States)
  • 5. CEA Cadarache, DEN-Dir, St-Paul-Lez-Durance (France)

Description

Highlights: • Thorium as support fertile material for TRU transmutation in Fast Reactors. • Comparative analysis of Th and U based breakeven and burner Fast Reactors. • Thorium fosters significant advantages in terms of safety parameters. • Inherent safety is investigated through quasi-static reactivity and energy balances. • Th use in low-CR Fast Reactors does not reduce fuel decay heat and neutron sources. - Abstract: The present paper compares the reactor physics and transmutation performance of sodium-cooled Fast Reactors (FRs) for TRansUranic (TRU) burning with thorium (Th) or uranium (U) as fertile materials. The 1000 MWt Toshiba-Westinghouse Advanced Recycling Reactor (ARR) conceptual core has been used as benchmark for the comparison. Both burner and breakeven configurations sustained or started with a TRU supply, and assuming full actinide homogeneous recycle strategy, have been developed. State-of-the-art core physics tools have been employed to establish fuel inventory and reactor physics performances for equilibrium and transition cycles. Results show that Th fosters large improvements in the reactivity coefficients associated with coolant expansion and voiding, which enhances safety margins and, for a burner design, can be traded for maximizing the TRU burning rate. A trade-off of Th compared to U is the significantly larger fuel inventory required to achieve a breakeven design, which entails additional blankets at the detriment of core compactness as well as fuel manufacturing and separation requirements. The gamma field generated by the progeny of U-232 in the U bred from Th challenges fuel handling and manufacturing, but in case of full recycle, the high contents of Am and Cm in the transmutation fuel impose remote fuel operations regardless of the presence of U-232

Availability note (English)

Available from http://dx.doi.org/10.1016/j.anucene.2013.06.001

Additional details

Identifiers

DOI
10.1016/j.anucene.2013.06.001;
PII
S0306-4549(13)00301-0;

Publishing Information

Journal Title
Annals of Nuclear Energy (Oxford)
Journal Volume
62
Journal Page Range
p. 26-39
ISSN
0306-4549
CODEN
ANENDJ

Optional Information

Copyright
Copyright (c) 2013 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.