锕系元素燃烧对尤卡山废弃物处理的影响

J. Hirschfelder, P. Chambré, W.W.-L. Lee, T. Pigford, M. Sadeghi
{"title":"锕系元素燃烧对尤卡山废弃物处理的影响","authors":"J. Hirschfelder, P. Chambré, W.W.-L. Lee, T. Pigford, M. Sadeghi","doi":"10.2172/140748","DOIUrl":null,"url":null,"abstract":"Partitioning the actinides in spent fuel and transmuting them in actinide-burning liquid-metal reactors (ALMRs) is a potential method of reducing public risks from the geologic disposal of nuclear waste. In this paper, the authors present a comparison of radionuclide releases from burial at Yucca Mountain of spent fuel and of ALMR wastes. Two waste disposal schemes are considered. In each, the heat generation of the wastes at emplacement is 9.88 {times} 10{sup 7} W, the maximum for the repository. In the first scheme, the repository contains 86,700 tonnes of initial heavy metal (IHM) of light water reactor (LWR) spent fuel. In the second scheme, all current LWRs operate for a 40-yr lifetime, producing a total of 84,000 tonnes IHM of spent fuel. This spent fuel is treated using a pyrochemical process in which 98.4% of the uranium and 99.8% of the neptunium, plutonium, americium, and curium are extracted and fabricated into ALMR fuel, with the reprocessing wastes destined for the repository. The ALMR requires this fuel for its startup and first two reloads; thereafter, it is self-sufficient. Spent ALMR fuel is also pyrochemically reprocessed: 99.9% of the transuranics is recovered and recycled into ALMR fuel, and the wastes are placedmore » in the repository. Thus, in the second scheme, the repository contains the wastes from reprocessing all of the LWR spent fuel plus the maximum amount of ALMR reprocessing wastes allowed in the repository based on its heat generation limit.« less","PeriodicalId":23138,"journal":{"name":"Transactions of the American Nuclear Society","volume":null,"pages":null},"PeriodicalIF":0.0000,"publicationDate":"1991-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"3","resultStr":"{\"title\":\"Effects of actinide burning on waste disposal at Yucca Mountain\",\"authors\":\"J. Hirschfelder, P. Chambré, W.W.-L. Lee, T. Pigford, M. Sadeghi\",\"doi\":\"10.2172/140748\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"Partitioning the actinides in spent fuel and transmuting them in actinide-burning liquid-metal reactors (ALMRs) is a potential method of reducing public risks from the geologic disposal of nuclear waste. In this paper, the authors present a comparison of radionuclide releases from burial at Yucca Mountain of spent fuel and of ALMR wastes. Two waste disposal schemes are considered. In each, the heat generation of the wastes at emplacement is 9.88 {times} 10{sup 7} W, the maximum for the repository. In the first scheme, the repository contains 86,700 tonnes of initial heavy metal (IHM) of light water reactor (LWR) spent fuel. In the second scheme, all current LWRs operate for a 40-yr lifetime, producing a total of 84,000 tonnes IHM of spent fuel. This spent fuel is treated using a pyrochemical process in which 98.4% of the uranium and 99.8% of the neptunium, plutonium, americium, and curium are extracted and fabricated into ALMR fuel, with the reprocessing wastes destined for the repository. The ALMR requires this fuel for its startup and first two reloads; thereafter, it is self-sufficient. Spent ALMR fuel is also pyrochemically reprocessed: 99.9% of the transuranics is recovered and recycled into ALMR fuel, and the wastes are placedmore » in the repository. Thus, in the second scheme, the repository contains the wastes from reprocessing all of the LWR spent fuel plus the maximum amount of ALMR reprocessing wastes allowed in the repository based on its heat generation limit.« less\",\"PeriodicalId\":23138,\"journal\":{\"name\":\"Transactions of the American Nuclear Society\",\"volume\":null,\"pages\":null},\"PeriodicalIF\":0.0000,\"publicationDate\":\"1991-11-01\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"3\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Transactions of the American Nuclear Society\",\"FirstCategoryId\":\"1085\",\"ListUrlMain\":\"https://doi.org/10.2172/140748\",\"RegionNum\":0,\"RegionCategory\":null,\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"\",\"JCRName\":\"\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Transactions of the American Nuclear Society","FirstCategoryId":"1085","ListUrlMain":"https://doi.org/10.2172/140748","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}
引用次数: 3

摘要

对乏燃料中的锕系元素进行分解,并在锕系元素燃烧的液态金属反应堆(ALMRs)中对其进行嬗变,是减少核废料地质处置带来的公共风险的一种潜在方法。本文对尤卡山掩埋乏燃料和ALMR废弃物释放的放射性核素进行了比较。考虑了两种废物处置方案。在每个反应堆中,废料放置时产生的热量为9.88 {times} 10{sup 7} W,这是贮存库的最大值。在第一个方案中,储存库包含86,700吨轻水反应堆(LWR)乏燃料的初始重金属(IHM)。在第二个方案中,所有现有的轻水堆的运行寿命为40年,产生总共84,000吨IHM的乏燃料。这种乏燃料使用热化学过程进行处理,其中98.4%的铀和99.8%的镎、钚、镅和curium被提取并制造成ALMR燃料,后处理废物被送往储存库。ALMR在启动和前两次重新装载时需要这种燃料;此后,它是自给自足的。用过的ALMR燃料也经过热化学再处理:99.9%的超铀元素被回收并再循环成ALMR燃料,而废物则被更多地放置在储存库中。因此,在第二种方案中,储存库包含所有轻水堆乏燃料再处理产生的废物,加上储存库根据其产热限制允许的ALMR再处理废物的最大数量。«少
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Effects of actinide burning on waste disposal at Yucca Mountain
Partitioning the actinides in spent fuel and transmuting them in actinide-burning liquid-metal reactors (ALMRs) is a potential method of reducing public risks from the geologic disposal of nuclear waste. In this paper, the authors present a comparison of radionuclide releases from burial at Yucca Mountain of spent fuel and of ALMR wastes. Two waste disposal schemes are considered. In each, the heat generation of the wastes at emplacement is 9.88 {times} 10{sup 7} W, the maximum for the repository. In the first scheme, the repository contains 86,700 tonnes of initial heavy metal (IHM) of light water reactor (LWR) spent fuel. In the second scheme, all current LWRs operate for a 40-yr lifetime, producing a total of 84,000 tonnes IHM of spent fuel. This spent fuel is treated using a pyrochemical process in which 98.4% of the uranium and 99.8% of the neptunium, plutonium, americium, and curium are extracted and fabricated into ALMR fuel, with the reprocessing wastes destined for the repository. The ALMR requires this fuel for its startup and first two reloads; thereafter, it is self-sufficient. Spent ALMR fuel is also pyrochemically reprocessed: 99.9% of the transuranics is recovered and recycled into ALMR fuel, and the wastes are placedmore » in the repository. Thus, in the second scheme, the repository contains the wastes from reprocessing all of the LWR spent fuel plus the maximum amount of ALMR reprocessing wastes allowed in the repository based on its heat generation limit.« less
求助全文
通过发布文献求助,成功后即可免费获取论文全文。 去求助
来源期刊
自引率
0.00%
发文量
0
×
引用
GB/T 7714-2015
复制
MLA
复制
APA
复制
导出至
BibTeX EndNote RefMan NoteFirst NoteExpress
×
提示
您的信息不完整,为了账户安全,请先补充。
现在去补充
×
提示
您因"违规操作"
具体请查看互助需知
我知道了
×
提示
确定
请完成安全验证×
copy
已复制链接
快去分享给好友吧!
我知道了
右上角分享
点击右上角分享
0
联系我们:info@booksci.cn Book学术提供免费学术资源搜索服务,方便国内外学者检索中英文文献。致力于提供最便捷和优质的服务体验。 Copyright © 2023 布克学术 All rights reserved.
京ICP备2023020795号-1
ghs 京公网安备 11010802042870号
Book学术文献互助
Book学术文献互助群
群 号:481959085
Book学术官方微信