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Conference Article: Physics design of advanced heavy water reactor utilising thorium

Kumar, A.; Kannan, U.; Padala, Y.; Behera, G.M.; Srivenkatesan, R.; Balakrishnan, K. (Reactor Physics Design Section, Reactor Design and Development Group, Bhabha Atomic Research Centre, Mumbai (India))

Abstract

An Advanced Heavy Water Reactor (AHWR) is being developed in India with the aim of utilising thorium for power generation. AHWR is a vertical pressure tube type reactor cooled by boiling light water and moderated by heavy water. It has been optimised for the thorium cycle. The main design objective is to be self-sustaining in 233U with most of the power from the thorium fuel using plutonium as the external fissile feed. It incorporates several advanced safety features namely, heat removal through natural circulation and a negative void coefficient of reactivity. The reactor has been designed to produce 750 MW(th) at a discharge burnup of 20,000 MWd/H(e). The physics design of AHWR has followed an evolutionary path ranging from a seed and blanket concept to a simplified composite cluster to achieve a good thermal hydraulic coupling. We have designed a composite cluster using both kinds of fuel namely, (Th-UO2 and (Th-Pu)O2. With plutonium seed, negative void coefficient can be achieved by making the spectrum harder. This was done by using a pyrocarbon scatterer in the moderator. The void coefficient strongly depends on plutonium. As plutonium burns very rapidly, it is not possible to achieve uniformly negative void coefficient with burnup in this cluster. Alternatively, burnable poison can be used within the cluster to achieve negative void coefficient taking advantage of the flux redistribution and change in spectrum upon voiding. Here, it is possible to achieve almost constant void reactivity with burnup resulting in a good thermal hydraulic coupling. The cluster design presently incorporates a central burnable absorber region. Boiling light water coolant requires that the core power distribution be optimised with thermal hydraulic parameters. The peaking factors inside the cluster should be low so as to have significant margin in operational conditions and to avoid burnout in accident conditions. The variation of reactivity from cold clean to hot operating has been evaluated. In this paper, results of the core calculations, neutronic-thermal hydraulic coupling, reactivity swings and kinetic parameters were presented.

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key words: bhwr type reactors; burnup; fuel element clusters; fuel pellets; plutonium; reactivity; reactor kinetics; thorium cycle

Reference:: Proceedings of three IAEA meetings held in Vienna in 1997, 1998 and 1999; International Atomic Energy Agency, Vienna (Austria); IAEA-TECDOC--1319, pp:165-175