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Normalizing the maximum permissible seal failure of the fuel cladding of VVÉR and the activity of the fission products in the coolant

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References

  1. Code of Federal Regulations. Title 10: Energy, Pt. 50, Washington (1981).

  2. Standard Review Plan. Sect. 4.2: Fuel System Design, NUREC-0800 (1981).

  3. Onsite Nondestructive Examination Techniques for Irradiated Water-Cooled Power Reactor Fuel, IAEA-TECDOC-245, Vienna (1981).

  4. R. Yang et al., “Fuel performance evaluation for EPRI program planning,” in: Proc. Int. Top. Meeting on LWR Fuel Performance “Fuel for the 90's,” Vol. 1, Avignon, France, April 21–24, 1991, pp. 258-271.

  5. D. Locke, Ramifications of the Presence of Ejected Fuel on LWR Power Reactor Operations, Proc. Spec. Meetings in Chalk River, Canada, 17–21 Sept., 1979, IAEA-IWGFPT/6 (1979).

  6. “Operating characteristics of fuel elements of light water reactors in the USA,” Atom. Tekh. Rubezh., No. 8, 23-26 (1983).

  7. L. M. Luzanova and P. D. Slavyagin, The Escape of Radioactive Fission Products from Nonhermetic Fuel Elements Based on Baked Uranium Dioxide [in Russian], Preprint IAÉ-3723/4 (1983).

  8. Procedure for Calculating Escape of Radioactive Products Fuel Elements and Outside of Primary Circuit for Normal Operation and during Emergencies. Normative-Technical Document of Unified Group of Comecon Countries in Field of Nuclear Power Engineering [in Russian], Coordinated Project, June, 1989 (1989).

  9. Rules for Nuclear Safety of Reactor Installations at PBYa RU AS-89 Nuclear Power Stations [in Russian], Énergoatomizdat, Moscow (1990).

  10. Instructions for Monitoring the Seal of Fuel Claddings of VVÉR-1000 Reactors during Operation and after Shutdown of the Equipment [in Russian], 0401.00.00.000.DNG (1980).

  11. Instructions for Monitoring the Seal of Fuel Claddings of VVÉR-440 Reactors (Types V-230 and V-213) during Operation and after Shutdown of Equipment [in Russian], 62444-OZDIK-LU (1985).

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Authors
  1. L. M. Luzanova
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  2. V. N. Miglo
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  3. P. D. Slavyagin
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Additional information

I. V. Kurchatov Institute of Atomic Energy, Russian Science Center. Translated from Atomnaya Énergiya, Vol. 74, No. 6, pp. 491-497, June, 1993.

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Luzanova, L.M., Miglo, V.N. & Slavyagin, P.D. Normalizing the maximum permissible seal failure of the fuel cladding of VVÉR and the activity of the fission products in the coolant. At Energy 74, 458–463 (1993). https://doi.org/10.1007/BF00739163

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  • DOI: https://doi.org/10.1007/BF00739163

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