A physics study on alternative reflectors in a compact sodium-cooled breed-and-burn fast reactor

Donny Hartanto, Yonghee Kim

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

2 Scopus citations

Abstract

The breed-and-burn reactor (B&BR), also known as the Traveling Wave Reactor, is a unique fast reactor concept thatoffers attractive characteristics in terms of core performance, economics, and non-proliferation aspects. The B&BR has the ability tobreed its own fuel and use itin situ to achieve an extremely long life. A previous study of the neutronics of small and compact sodium-cooled B&BR to re-utilize the PWR spent fuel found that several concerns should be solved in order to increase the safety and performance of the B&BR. One of the most concerning safety issues is the relatively large sodium void reactivity, about 7~8. One approach to reduce the sodium void reactivity coefficient is by enhancing the leakagefrom the core. This can be done in two ways: axially or radially. Since the reactor height needs to be sufficiently high to achieve the breed and burn state, it is not an option to increase the axial leakage by reducing the core height. Instead, alternative radial reflector designs are investigated in order to improve the sodium void reactivity and density coefficient of the B&BR. In most of sodium-cooled fast reactors, a tight lattice of steel (HT-9) rods is used as the reflector assembly. In this study, we introduced a lead or Pb and Mg eutectic (LME) alloy as the radial reflector for an improved performance of the B&BR. The liquid Pb and LME are contained in HT-9 clad and a single reflector assembly consists of the Pb-or LME-containing rods. In addition, we also compare anMgO reflector with the Pb or LME reflectors. Impacts of the various reflector materials and reflector configurations are identified in terms of the reactor performance and safety parameters includingthe sodium void reactivity. The calculations were done using the Monte Carlo code McCARD.

Original languageEnglish
Title of host publicationInternational Congress on Advances in Nuclear Power Plants, ICAPP 2013
Subtitle of host publicationNuclear Power - A Safe and Sustainable Choice for Green Future, Held with the 28th KAIF/KNS Annual Conference
PublisherKorean Nuclear Society
Pages1754-1760
Number of pages7
ISBN (Electronic)9781632660381
StatePublished - 2013
Externally publishedYes
EventInternational Congress on Advances in Nuclear Power Plants: Nuclear Power - A Safe and Sustainable Choice for Green Future, ICAPP 2013, Held with the 28th KAIF/KNS Annual Conference - Jeju Island, Korea, Republic of
Duration: Apr 14 2013Apr 18 2013

Publication series

NameInternational Congress on Advances in Nuclear Power Plants, ICAPP 2013: Nuclear Power - A Safe and Sustainable Choice for Green Future, Held with the 28th KAIF/KNS Annual Conference

Conference

ConferenceInternational Congress on Advances in Nuclear Power Plants: Nuclear Power - A Safe and Sustainable Choice for Green Future, ICAPP 2013, Held with the 28th KAIF/KNS Annual Conference
Country/TerritoryKorea, Republic of
CityJeju Island
Period04/14/1304/18/13

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