Preliminary Study of Severe Accident Source Term for Emergency Facility Habitability

被引:0
|
作者
Sun D.-W. [1 ]
Fu Y.-R. [1 ]
Mei Q.-L. [1 ]
Zhang S.-S. [1 ]
Pan N. [1 ]
机构
[1] Shanghai Nuclear Engineering Research & Design Institute, Shanghai
关键词
Emergency facility habitability; Radiation influence; Severe accident;
D O I
10.7538/yzk.2017.51.07.1322
中图分类号
学科分类号
摘要
Based on advanced pressurized water reactor nuclear plant, research on severe accident source terms for emergency facility habitability was carried out, including core inventory release, nuclide removal in containment and release pathways to environment. Considering the feature of passive containment cooling system, the prospective failure behaviors for containment were mainly studied, and radiation influences based on containment failure at 24 h and 72 h were estimated. The results show that the radioactive release levels for both conditions reach level 6 of INES (international nuclear and radiological event scale). The radioactive fractions of 133Xe released into environment lie between PWR2-PWR4 of WASH-1400, and the radioactive fractions of 131I released into environment lie between PWR5-PWR6 of WASH-1400. Meanwhile, based on the coastal site in China, operator doses of emergency operation facility (EOF) were assessed, which meet the dose limit value of 100 mSv. © 2017, Editorial Board of Atomic Energy Science and Technology. All right reserved.
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页码:1322 / 1327
页数:5
相关论文
共 10 条
  • [1] NUREG-0396 Planning basis for the development of state and local government radiological emergency response plans in support of light water nuclear power plants, (1978)
  • [2] RG 1.183 Alternative radiological source terms for evaluating design basis accidents at nuclear power reactors, (2000)
  • [3] NUREG-1465 Accident source terms for light-water nuclear power plants, (1995)
  • [4] NUREG-0800 Standard review plan (SRP) for the review of safety analysis reports for nuclear power plants, (2007)
  • [5] Sun D., Mei Q., Fu Y., Et al., AP1000 loss of coolant accident radiological consequence assessment based on AST method, Nuclear Science and Engineering, 36, 1, pp. 103-108, (2016)
  • [6] James M., Policy, Technical, and Licensing Issues Pertaining to Evolutionary and Advanced Light-water Reactor (ALWR) Designs, SECY-93-087, (1993)
  • [7] Eckerman K.F., Wolbarst A.B., Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion, pp. 121-153, (1988)
  • [8] Eckerman K.F., Jeffrey C.R., External Exposure to Radionuclides in Air, Water and Soil, pp. 58-73, (1993)
  • [9] The International Nuclear and Radiological Event Scale User's Manual, (2008)
  • [10] Reactor Safety Study: an Assessment of Accident Risk in U. S. Commercial Nuclear Power Plant, WASH-1400, (1975)