摘要
本文中介绍的我们设计的 ADHLW 程序能计算高放废物固化体内放射性总活度和主要核素的活度,及其内、外剂量率随时间和空间的变化。本程序可为我国高放废物深部地质处置安全和环境影响评价提供源项参数。为验证本程序,以美国76—68硼硅酸盐废物玻璃固化体处置在深部地质中为例,用本程序进行了计算,并与美国 WAPPA 程序的计算结果和有关文献报道值进行了比较,结果在10—15%内符合。
This paper introduces a computer code——ADHLW designed for calculatingthe radioactivity of each main radionuclide and the total radioactivity in high-level waste(HLW)solidified products,as well as for the distance and time-dependent dose rate insideand outside the solidified products.The code will be useful for siting and designingHLW repository in deep rock formation,and will provide a basis for the assessment ofdisposal project and its environmental impact.For validation,we have calculated the76-68 borosilicate glass waste solidified products and compared the results obtained withthat of WAPPA code of USDOE,and with others.All results are comparable withinabout 10—15%.
出处
《辐射防护》
CAS
CSCD
北大核心
1991年第1期23-33,共11页
Radiation Protection
关键词
高放废物
放射性活度
固化体
程序
Computer Code
High-level Waste
Solidified Products
Waste Disposal
Radioactivity
Dose Rate
