Correlation between potential radiation-induced carcinogenic risks associated with WWER-1000 spent nuclear fuel and BREST-1200 radiation waste in case of annual generation of 1 GW of electricity. Part 1. Radiological equivalence

V. Ivanov, A. Lopatkin, E. Adamov, A. Menyajlo, S. Chekin, P. Kashcheeva, A. M. Korelo, K. Tumanov
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Abstract

The paper presents for the first-time comparison of radiation safety for the population between spent nuclear fuel (SNF) irradiated in water-water power reactor with thermal neutrons (WWER-1000) and radioactive wastes (RW) from lead cooled fast neutrons reactor (BREST-1200). The re-actors generate equal amount of electric power 1 GW per year. Composition and radiation param-eters of long-lived radiation wastes sent to disposal is reviewed. Potential biological hazards from SNF and RW for about 10,000-years disposal were estimated as effective doses (Sv). To assess potential radiation-induced carcinogenic risk as estimates of lifetime attributable risk (LAR) new ICRP methodology was used. New ICRP methodology was used as the basis for the computer code for the program “Radiological protection of the population” (ROZA-N) developed by the Proryv Project of the Rosatom State Corporation. The project was registered at the Unified Register of Russian Software in 2021 (registration number 2442). It was found that potential radiation-induced carcinogenic risk for the population associated with WWER-1000 reactor SNF was 132 times high-er than the risk associated with BREST-1200 reactor RW. Radiological equivalence of carcinogenic risks associated with SNF WWER-1000 and natural uranium material was proven to be achieved in about 15,600 years (significantly more than 10,000 years), the radiological equivalence of risks associated with RW BREST-1200, on the other hand, to be achieved only in 120 years.
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在年发电量为1gw的情况下,WWER-1000乏核燃料与BREST-1200辐射废物潜在辐射致癌风险的相关性第1部分。辐射等效
本文首次比较了在热中子水-水动力堆(WWER-1000)中辐照过的乏燃料(SNF)和铅冷快中子堆(BREST-1200)中的放射性废料(RW)在人群中的辐射安全性。这些反应堆每年产生1吉瓦的电力。综述了外送处置的长寿命放射性废物的组成和辐射参数。按有效剂量(西沃特)估计了处置约1万年SNF和RW的潜在生物危害。为了评估潜在的辐射致癌风险作为终身归因风险(LAR)的估计,使用了新的ICRP方法。新的ICRP方法被用作俄罗斯国家原子能公司普罗里夫项目制定的“人口辐射防护”(ROZA-N)程序的计算机代码的基础。该项目于2021年在俄罗斯软件统一登记处注册(注册号2442)。研究发现,与WWER-1000反应堆SNF相关的人群的潜在辐射致癌风险比与BREST-1200反应堆RW相关的风险高132倍。与SNF WWER-1000和天然铀材料相关的致癌风险的放射等效已被证明在大约15,600年(大大超过10,000年)内实现,而与RW BREST-1200相关的风险的放射等效仅在120年内实现。
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