首页> 外文会议>International nuclear fuel cycle conference >MINOR ACTINIDE TRANSMUTATION IN THORIUM AND URANIUM MATRICES IN HEAVY WATER MODERATED REACTORS
【24h】

MINOR ACTINIDE TRANSMUTATION IN THORIUM AND URANIUM MATRICES IN HEAVY WATER MODERATED REACTORS

机译:重水中和反应器中T和铀基质中的微量丙烯转化

获取原文

摘要

The irradiation of Th-232 breeds fewer of the problematic minor actinides (Np, Am, Cm) than the irradiation of U-238. This characteristic makes thorium an attractive potential matrix for the transmutation of these minor actinides, as these species can be transmuted without the creation of new actinides as is the case with a uranium fuel matrix. Minor actinides are the main contributors to long term decay heat and radiotoxicity of spent fuel, so reducing their concentration can greatly increase the capacity of a long term deep geological repository. Mixing minor actinides with thorium, three times more common in the Earth's crust than natural uranium, has the additional advantage of improving the sustainability of the fuel cycle. In this work, lattice cell calculations have been performed to determine the results of transmuting minor actinides from light water reactor spent fuel in a thorium matrix. 15-year-cooled group-extracted transuranic elements (Np, Pu, Am, Cm) from light water reactor (LWR) spent fuel were used as the fissile component in a thorium-based fuel in a heavy water moderated reactor (HWR). The minor actinide (MA) transmutation rates, spent fuel activity, decay heat and radiotoxicity, are compared with those obtained when the MA were mixed instead with natural uranium and taken to the same burnup. Each bundle contained a central pin containing a burnable neutron absorber whose initial concentration was adjusted to have the same reactivity response (in units of the delayed neutron fraction β)for coolant voiding as standard NU fuel.
机译:与U-238的照射相比,Th-232的照射产生的有问题的次act系元素(Np,Am,Cm)更少。这种特性使th成为这些次act系元素trans变的有吸引力的潜在基质,因为这些物种可以被can变而不会产生新的act系元素,就像铀燃料基质一样。次要act系元素是乏燃料的长期衰变热和放射毒性的主要贡献者,因此降低其浓度可以大大提高长期深部地质处置库的能力。将微量act系元素与or混合(在地壳中的含量是天然铀的三倍),具有改善燃料循环可持续性的额外优势。在这项工作中,已经进行了晶格计算,以确定from基质中轻水反应堆乏燃料对次act系元素进行trans变的结果。来自轻水反应堆(LWR)乏燃料的15年冷却的群萃取超铀元素(Np,Pu,Am,Cm)被用作重水缓和反应堆(HWR)中or基燃料的易裂变组分。将次act系元素(MA)的rates变速率,乏燃料活性,衰变热和放射毒性与将MA代替天然铀混合并进行相同燃耗时的结果进行了比较。每个束包含一个中心销,该中心销包含可燃烧的中子吸收剂,该中子吸收剂的初始浓度被调整为具有与标准NU燃料相同的冷却剂排空反应性(以延迟中子分数β的单位)。

著录项

相似文献

  • 外文文献
  • 中文文献
  • 专利
获取原文

客服邮箱:kefu@zhangqiaokeyan.com

京公网安备:11010802029741号 ICP备案号:京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有
  • 客服微信

  • 服务号