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Initiating Events Study of the First Extraction Cycle Process in a Model Reprocessing Plant

  • Received : 2015.07.17
  • Accepted : 2016.06.07
  • Published : 2016.06.30

Abstract

Background: Definition and grouping of initiating events (IEs) are important basics for probabilistic safety assessment (PSA). An IE in a spent fuel reprocessing plant (SFRP) is an event that probably leads to the release of dangerous material to jeopardize workers, public and environment. The main difference between SFRPs and nuclear power plants (NPPs) is that hazard materials spread diffusely in a SFRP and radioactive material is just one kind of hazard material. Materials and Methods: Since the research on IEs for NPPs is in-depth around the world, there are several general methods to identify IEs: reference of lists in existence, review of experience feedback, qualitative analysis method, and deductive analysis method. While failure mode and effect analysis (FMEA) is an important qualitative analysis method, master logic diagram (MLD) method is the deductive analysis method. IE identification in SFRPs should be consulted with the experience of NPPs, however the differences between SFRPs and NPPs should be considered seriously. Results and Discussion: The plutonium uranium reduction extraction (Purex) process is adopted by the technics in a model reprocessing plant. The first extraction cycle (FEC) is the pivotal process in the Purex process. Whether the FEC can function safely and steadily would directly influence the production process of the whole plant-production quality. Important facilities of the FEC are installed in the equipment cells (ECs). In this work, IEs in the FEC process were identified and categorized by FMEA and MLD two methods, based on the fact that ECs are containments in the plant. Conclusion: The results show that only two ECs in the FEC do not need to be concerned particularly with safety problems, and criticality, fire and red oil explosion are IEs which should be emphatically analyzed. The results are accordant with the references.

Keywords

References

  1. International Atomic Energy Agency. Procedures for conducting probabilistic safety assessment for non-reactor nuclear facilities. IAEA-TECDOC-1267. 2002;1-10.
  2. International Atomic Energy Agency. Procedures for conducting probabilistic safety assessments of nuclear power plants (Level 1). Safety Series No. 50-P-4. 1992;28-30.
  3. Walls SJ. Applications of probabilistic risk assessment at BNFL, Sellafield. The International Topical Meeting on Safety Margins in Criticality Safety. La Grange Park USA. November 26-December 1, 1989.
  4. Bowers WJ. Probabilistic risks assessment applied to nuclear chemical and waste management plants. Czechoslovak-British Nuclear Power Seminar. Prague Czechoslovakia. November 8-9, 1988.
  5. Sheppard GT, Taylor JB. The safety case for the thermal oxide reprocessing plant at Sellafield. Technical Committee Meeting of Use of Probabilistic Safety Assessment for Nuclear Installations with Large Inventory of Radioactive Material. Vienna Austria. September 7-11, 1992.
  6. Sunman CRJ, Campbell RJ, and Wakem MJ. Probabilistic risk assessment for back-end facilities: improving the treatment of fire and explosion scenarios. The First NUCEF International Symposium. Hitachinaka Japan. October 16-17, 1995.
  7. Sheppard GT, Williams RJ. PSA experience with fuel cycle plant. Nucl. Energy. 1993;32(6):363-367.
  8. Bowers WJ, Clemson PD, Page RJ. Recent developments in the safety assessment of nuclear chemical plants. The Third International Conference on Nuclear Fuel Reprocessing and Waste Management, RECOD'91. Tokyo Japan. April 14-18, 1991.
  9. Mercier JP, Bonneval F, Weber M. Application of the probabilistic approach to the UP3-A reprocessing plant. Technical Committee Meeting of Use of Probabilistic Safety Assessment for Nuclear Installations with Large Inventory of Radioactive Material. Vienna Austria. September 7-11, 1992.
  10. Ishida M, Nakano T, Morimoto K, and Nojiri I. PSA application on the Tokai reprocessing plant. The 11th International Conference on Nuclear Engineering. Tokyo Japan. April 20-23, 2003.
  11. Ren FY, Zhou ZX. Foreign nuclear fuel reprocessing. 1st ed. Beijing. Atomic Energy Press. 2006;106-173.
  12. Jiang SJ, Ren FY. Nuclear fuel reprocessing engineering science. 1st ed. Beijing. Atomic Energy Press. 1995;158-196.
  13. Zheng H, Zhao B, Li RR. Primary research of probabilistic safety assessment for spent fuel plant. Nuclear engineering study and design. 2008; 69:30-36.