• A conceptual high flux reactor design with scope for use in ADS applications

• # Fulltext

Permanent link:
https://www.ias.ac.in/article/fulltext/pram/068/02/0151-0159

• # Keywords

High flux reactor; thermal neutron flux traps; fast neutron flux traps; long fuel cycle duration.

• # Abstract

A 100 MWt reactor design has been conceived to support flux level of the order of 1015 n/cm2/s in selected flux trap zones. The physics design considers high enriched metallic alloy fuel in the form of annular plates placed in a D2O moderator tank in a hexagonal lattice arrangement. By choosing a tight lattice pitch in the central region and double the lattice pitch in the outer region, it is possible to have both high fast flux and thermal flux trap zones. By design the flux level in the seed fuel has been kept lower than in the high flux trap zones so that the burning rate of the seed is reduced. Another important objective of the design is to maximize the time interval of refueling. As against a typical refueling interval of a few weeks in such high flux reactor cores, it is desired to maximize this period to as much as six months or even one year. This is possible to achieve by eliminating the conventional control absorbers and replacing them with a suitable amount of fertile material loading in the reactor. Requisite number of seedless thorium–aluminum alloy plates are placed at regular lattice locations vacated by seed fuel in alternate fuel layers. It is seen that these thorium plates are capable of acquiring asymptotic fissile content of 14 g/kg in about 100 days of irradiation at a flux level of $8 \times 10^{14}$ n/cm2 /s. In summary, the core has a relatively higher fast flux in the central region and high thermal flux in the outer region. The present physics design envisages a flat core excess reactivity for the longest possible cycle length of 6 months to one year. It is also possible to modify the design for constant subcriticality for about the same period or longer duration by considering neutron spallation source at the centre and curtailing the power density in the inner core region by shielding it with a layer of thoria fuel loading.

• # Author Affiliations

1. Reactor Physics Division, Bhabha Atomic Research Centre, Trombay, Mumbai 400 085, India

• # Pramana – Journal of Physics

Volume 94, 2020
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• # Editorial Note on Continuous Article Publication

Posted on July 25, 2019

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