Spent fuel utilization in a compact traveling wave reactor

Donny Hartanto, Yonghee Kim

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

2 Scopus citations

Abstract

In recent years, several innovative designs of nuclear reactors are proposed. One of them is Traveling Wave Reactor (TWR). The unique characteristic of a TWR is the capability of breeding its own fuel in the reactor. The reactor is fueled by mostly depleted, natural uranium or spent nuclear fuel and a small amount of enriched uranium to initiate the fission process. Later on in the core, the reactor gradually converts the non-fissile material into the fissile in a process like a traveling wave. In this work, a TWR with spent nuclear fuel blanket was studied. Several parameters such as reactivity coefficients, delayed neutron fraction, prompt neutron generation lifetime, and fission power, were analyzed. The discharge burnup composition was also analyzed. The calculation is performed by a continuous energy Monte Carlo code McCARD.

Original languageEnglish
Title of host publication3rd International Conference on Advances in Nuclear Science and Engineering 2011, ICANSE 2011
Pages65-73
Number of pages9
DOIs
StatePublished - 2012
Externally publishedYes
Event3rd International Conference on Advances in Nuclear Science and Engineering 2011, ICANSE 2011 - Bali, Indonesia
Duration: Nov 14 2011Nov 17 2011

Publication series

NameAIP Conference Proceedings
Volume1448
ISSN (Print)0094-243X
ISSN (Electronic)1551-7616

Conference

Conference3rd International Conference on Advances in Nuclear Science and Engineering 2011, ICANSE 2011
Country/TerritoryIndonesia
CityBali
Period11/14/1111/17/11

Keywords

  • McCARD
  • Spent nuclear fuel
  • TWR

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