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Conference papers

Study of CANDU thorium-based fuel cycles by deterministic and Monte Carlo methods

Abstract : In the framework of the Generation IV forum, there is a renewal of interest in self-sustainable thorium fuel cycles applied to various concepts such as Molten Salt Reactors [1,2] or High Temperature Reactors [3,4]. Precise evaluations of the U-233 production potential relying on existing reactors such as PWRs [5] or CANDUs [6] are hence necessary. As a consequence of its design (online refueling and D2O moderator in a thermal spectrum), the CANDU reactor has moreover an excellent neutron economy and consequently a high fissile conversion ratio [7]. For these reasons, we try here, with a shorter term view, to re-evaluate the economic competitiveness of once-through thorium-based fuel cycles in CANDU [8]. Two simulation tools are used: the deterministic Canadian cell code DRAGON [9] and MURE [10], a C++ tool for reactor evolution calculations based on the Monte Carlo code MCNP [11].
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Submitted on : Tuesday, October 3, 2006 - 2:49:18 PM
Last modification on : Thursday, January 7, 2021 - 3:28:03 PM
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A. Nuttin, P. Guillemin, T. Courau, G. Marleau, O. Méplan, et al.. Study of CANDU thorium-based fuel cycles by deterministic and Monte Carlo methods. PHYSOR-2006 Topical Meeting on Advances in Nuclear Analysis and Simulation, Sep 2006, Vancouver B.C., Canada. C111 (10 p.). ⟨in2p3-00103127⟩

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