铅铋反应堆放射性源项计算与剂量评估研究
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摘要
放射性源项计算研究放射性核素种类、数量、形态,以及在不同系统之间的迁移过程,它可以为反应堆的屏蔽设计、废物评估和环境影响分析提供参考。铅铋反应堆是快中子反应堆,与压水堆在冷却剂、保护气体等结构和材料上有明显区别。铅铋堆放射性源项也有自身的特点,特别是铅铋活化产生的易挥发放射性核素210Po,是铅铋反应堆设计时必须考虑的放射性问题。因此,本文基于中科院核能安全技术研究所·FDS团队设计的一个10MW铅铋反应堆方案,研究了放射性源项在铅铋反应堆各系统的分布,以及反应堆正常运行时的辐射场分布和事故时对公众的剂量。
本文使用了"MCNP-FISPACT"耦合活化计算方法开展了铅铋反应堆材料的活化计算,得到了铅铋反应堆各系统材料的放射性特性,包括活度、余热、接触剂量率和潜在生物危害。然后,根据铅铋反应堆中放射性核素的迁移特性和反应堆的结构特点,建立了铅铋反应堆中放射性核素在不同系统之间的迁移方程。并分析铅铋反应堆正常运行情况下,放射性源项在堆芯、一回路冷却剂、覆盖气体、二回路冷却剂、堆顶包容小室中的分布情况和每年向环境排放的放射性源项,并评估了铅铋反应堆正常运行时周围的剂量场分布。在分析铅铋堆放射性源项分布特点的基础上,选取了三种有放射性释放的铅铋堆事故,分别评估了三种事故后铅铋堆向环境排放的放射性源项,以及在非居住区边界上对公众造成的有效剂量。
通过本文分析,铅铋反应堆正常运行期间,堆顶包容小室中剂量率为0.126Sv/h,主要来自于堆芯产生的中子,此时堆顶包容小室属于极高辐射区,禁止人员进入。堆顶包容小室中气载放射性核素的有效剂量率为2.81mSv/h,主要来源于裂变气体Kr、Xe,而210Po的有效剂量率仅为4.49×10-17Sv/h。反应堆正常运行期间,每年向环境中排放的放射性核素总活度为2.58×1014Bq。当铅铋反应堆发生放射性核素释放事故时,包括双层容器破口事故、一回路覆盖气体系统泄漏事故和热交换器二次侧出口管道破口事故,对非居住区边界500m处公众个人(成人)0-2h期间的有效剂量都低于《GB6249-2011核动力厂环境辐射防护规定》的限值(5mSv),说明了此铅铋反应堆并不会对环境造成超过国标限值的严重后果。
Radioactive source term is defined as composition, quantity, form and transport of radionuclides between systems in the reactor. This could provide reference for shielding design, radioactive waste evaluation and environmental impact assessment. Lead-bismuth eutectic (LBE) cooled reactor is fast reactor, and different from PWR on coolant, cover gas, structure and etc. Radioactive source term is also characteristic. Especially, volatile polonium is needed to be considered for lead-bismuth reactor, which is produced by lead bismuth coolant activation. Therefore, a lead-bismuth eutectic cooled reactor design was applied, which was developed by Institute of Nuclear Energy Safety and Technology, Chinese Academy of Sciences-FDS Team. The distribution of radioactive source term in the lead-bismuth reactor was calculated. Then dose rate on personnel during normal operation and on public after the accidents was evaluated.
MCNP-FISPACT coupling activation calculation method was applied for LBE cooled reactor. Parametric study of material activation was conducted, including radioactivity, decay heat, contact dose rate and biological hazard potential. Then radionuclide balance equation was established based on characteristics of radionuclide transport regulation and structure design of LBE cooled reactor. The transport of radioactive source term between reactor core, primary coolant, cover gas, secondary coolant and containment room was calculated during normal operation, which was used for dose assessment and source term released to the environment. Three kinds of accident were selected for LBE cooled reactor, in which origin of radioactive source term is different. Radioactive source term released to environment was calculated and effective dose rate was evaluated at residential area boundary after accident.
During normal operation, the dose rate is0.126Sv/h in the containment room and mainly induced by neutrons. At that time, it is very high radiation area in the containment room and forbidden for personnel access. The effective dose rate from airborne radionuclides is2.81mSv/h, mainly induced by fission gas Krypton and Xenon. The total radioactivity of radionuclides emission to the environment is2.58×1014Bq each year. The personal dose at non-residential area boundary is lower than limit value of 《GB6249-2011Regulations for environmental radiation protection of nuclear power plant》 after radionuclide release accident, including breakage of double-walled container, leakage of cover gas system and breakage of secondary side outlet pipe in the heat exchanger. This shows that serious accident cannot happen in which personal dose is exceeded the national standard limit serious consequences.
本文使用了"MCNP-FISPACT"耦合活化计算方法开展了铅铋反应堆材料的活化计算,得到了铅铋反应堆各系统材料的放射性特性,包括活度、余热、接触剂量率和潜在生物危害。然后,根据铅铋反应堆中放射性核素的迁移特性和反应堆的结构特点,建立了铅铋反应堆中放射性核素在不同系统之间的迁移方程。并分析铅铋反应堆正常运行情况下,放射性源项在堆芯、一回路冷却剂、覆盖气体、二回路冷却剂、堆顶包容小室中的分布情况和每年向环境排放的放射性源项,并评估了铅铋反应堆正常运行时周围的剂量场分布。在分析铅铋堆放射性源项分布特点的基础上,选取了三种有放射性释放的铅铋堆事故,分别评估了三种事故后铅铋堆向环境排放的放射性源项,以及在非居住区边界上对公众造成的有效剂量。
通过本文分析,铅铋反应堆正常运行期间,堆顶包容小室中剂量率为0.126Sv/h,主要来自于堆芯产生的中子,此时堆顶包容小室属于极高辐射区,禁止人员进入。堆顶包容小室中气载放射性核素的有效剂量率为2.81mSv/h,主要来源于裂变气体Kr、Xe,而210Po的有效剂量率仅为4.49×10-17Sv/h。反应堆正常运行期间,每年向环境中排放的放射性核素总活度为2.58×1014Bq。当铅铋反应堆发生放射性核素释放事故时,包括双层容器破口事故、一回路覆盖气体系统泄漏事故和热交换器二次侧出口管道破口事故,对非居住区边界500m处公众个人(成人)0-2h期间的有效剂量都低于《GB6249-2011核动力厂环境辐射防护规定》的限值(5mSv),说明了此铅铋反应堆并不会对环境造成超过国标限值的严重后果。
Radioactive source term is defined as composition, quantity, form and transport of radionuclides between systems in the reactor. This could provide reference for shielding design, radioactive waste evaluation and environmental impact assessment. Lead-bismuth eutectic (LBE) cooled reactor is fast reactor, and different from PWR on coolant, cover gas, structure and etc. Radioactive source term is also characteristic. Especially, volatile polonium is needed to be considered for lead-bismuth reactor, which is produced by lead bismuth coolant activation. Therefore, a lead-bismuth eutectic cooled reactor design was applied, which was developed by Institute of Nuclear Energy Safety and Technology, Chinese Academy of Sciences-FDS Team. The distribution of radioactive source term in the lead-bismuth reactor was calculated. Then dose rate on personnel during normal operation and on public after the accidents was evaluated.
MCNP-FISPACT coupling activation calculation method was applied for LBE cooled reactor. Parametric study of material activation was conducted, including radioactivity, decay heat, contact dose rate and biological hazard potential. Then radionuclide balance equation was established based on characteristics of radionuclide transport regulation and structure design of LBE cooled reactor. The transport of radioactive source term between reactor core, primary coolant, cover gas, secondary coolant and containment room was calculated during normal operation, which was used for dose assessment and source term released to the environment. Three kinds of accident were selected for LBE cooled reactor, in which origin of radioactive source term is different. Radioactive source term released to environment was calculated and effective dose rate was evaluated at residential area boundary after accident.
During normal operation, the dose rate is0.126Sv/h in the containment room and mainly induced by neutrons. At that time, it is very high radiation area in the containment room and forbidden for personnel access. The effective dose rate from airborne radionuclides is2.81mSv/h, mainly induced by fission gas Krypton and Xenon. The total radioactivity of radionuclides emission to the environment is2.58×1014Bq each year. The personal dose at non-residential area boundary is lower than limit value of 《GB6249-2011Regulations for environmental radiation protection of nuclear power plant》 after radionuclide release accident, including breakage of double-walled container, leakage of cover gas system and breakage of secondary side outlet pipe in the heat exchanger. This shows that serious accident cannot happen in which personal dose is exceeded the national standard limit serious consequences.
引文
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