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Mitigation of end flux peaking in CANDU fuel bundles using neutron absorbers

  • Royal Military College of Canada
  • Canadian Nuclear Safety Commission

科研成果: 书/报告/会议事项章节会议稿件同行评审

摘要

End flux peaking (EFP) is a phenomenon where a region of elevated neutron flux occurs between two adjoining fuel bundles. These peaks lead to an increase in fission rate and therefore greater heat generation. It is known that addition of neutron absorbers into fuel bundles can help mitigate EFP, yet implementation in Canada Deuterium Uranium (CANDU) type reactors using natural uranium fuel has not been pursued. Monte Carlo N-Particle code (MCNP) 6.1 was used to simulate the addition of a small amount of neutron absorbers strategically within the fuel pellets. This paper will present some preliminary results collected thus far.

源语言英语
主期刊名Canadian Nuclear Society - 35th Annual Conference of the Canadian Nuclear Society and 38th CNS/CNA Student Conference 2015
出版商Canadian Nuclear Society
157-166
页数10
ISBN(电子版)9781510810815
出版状态已出版 - 2015
已对外发布
活动35th Annual Conference of the Canadian Nuclear Society and 38th CNS/CNA Student Conference 2015 - Saint John, 加拿大
期限: 31 5月 20152 6月 2015

出版系列

姓名Canadian Nuclear Society - 35th Annual Conference of the Canadian Nuclear Society and 38th CNS/CNA Student Conference 2015
1

会议

会议35th Annual Conference of the Canadian Nuclear Society and 38th CNS/CNA Student Conference 2015
国家/地区加拿大
Saint John
时期31/05/152/06/15

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