Study on the Framework of Fission Product Source Term for Nuclear Power Plants

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Abstract:

The problems occurring in the fission product source term calculations for M310/CPR1000, EPR and AP1000 are briefly analyzed, based on the related regulations and standards, as well as operational feedback, review experiences and recent research achievements for nuclear power plants in China. The framework of fission product source term proper to China has been first studied and proposed in perspective of the purpose of source terms. The calculation processes of fission product source term are rearranged and the requirements for deferent reactor types are specified. The proposed framework can be taken as a foundation for solution of the long-standing problems in the calculation of fission product source term and provide reference for source term calculation.

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Periodical:

Advanced Materials Research (Volumes 986-987)

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564-571

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Online since:

July 2014

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© 2014 Trans Tech Publications Ltd. All Rights Reserved

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[1] Lingdong Nuclear Power Co., Ltd., Final safety analysis report of LDNPC unit 3&4, (2009).

Google Scholar

[2] Liaoning Hongyanhe Nuclear Power Co., Ltd., Final safety analysis report of LHNPC unit 1&2, (2011).

Google Scholar

[3] Taishan Nuclear Power Joint Venture Co., Ltd., Final safety analysis report of TNPJVC unit 1&2, (2012).

Google Scholar

[4] Sanmen Nuclear Power Co., Ltd., Final safety analysis report of SMNPC unit 1&2, (2012).

Google Scholar

[5] NUREG-0017 Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Pressurized Water Reactors PWR-GALE Code, (1985).

DOI: 10.2172/5633355

Google Scholar

[6] ANSI/ANS-18. 1-1984. American National Standard Radioactive Source Term for Normal Operation of Light Water Reactors, (1984).

Google Scholar

[7] 10CFR20 Standards for Protection against Radiation, Appendix B. Annual Limits on Intake(ALIs) and Derived Air Concentration(DACs) of Radionuclides for Occupation Exposure; Effluent Concentrations; Concentrations for Release to Sewerage, (1991).

Google Scholar

[8] China Nuclear Power Technology Research Institute. Study on the optimization of primary coolant source terms—corrosion products and fission products, (2013).

Google Scholar