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Development of the Vacuum Drying Process for the PWR Spent Nuclear Fuel Dry Storage

경수로 사용후핵연료 건식저장을 위한 진공건조공정 개발

  • Received : 2016.10.07
  • Accepted : 2016.12.08
  • Published : 2016.12.31

Abstract

This paper describes the development of a dry operation process for PWR spent nuclear fuel, which is currently stored in the domestic NPP's storage pool, using a dual purpose metal cask. Domestic NNPs have had experience with wet type transportation of PWR spent nuclear fuel between neighboring NPPs since the early 1990s, but no experience with dry type operation. For this reason, we developed a specific operation process and also confirmed the safety of the major cask components and its spent nuclear fuel during the dual purpose metal cask operation process. We also describe the short term operation process that was established to be completed within 21 hours and propose the allowable working time for each step (15 hours for wet process, 3 hours for drain process and 3 hours for vacuum drying process).

본 논문은 국내 원전의 습식저장조에 저장 중인 경수로형 사용후핵연료를 금속겸용용기를 이용해 건식으로 운영하기 위한 운영공정을 개발하는 것이다. 국내 경수로형 원전의 사용후핵연료는 1990년대 초부터 습식으로 소내에서 운반을 한 경험은 많으나 건식으로 운전한 경험은 전혀 없는 실정이다. 이에 따라 금속겸용용기를 운영할 수 있는 세부 운영공정을 개발하였으며 주요 운영공정에서 금속겸용용기의 주요 구성품 및 사용후핵연료의 안전성이 유지됨을 확인하였다. 단기운영공정은 총 21시간 내에 이루어지도록 절차를 수립하였고 단계별로 허용운전 시간(15시간 습식공정, 3시간 배수공정, 그리고 3시간 진공공정)도 제시하였다.

Keywords

References

  1. U.S. Nuclear Regulatory Commission (NRC), Standard Review Plan for Dry Cask Storage Systems, NUREG-1536, Revision 1 (2010).
  2. Korea Radioactive Waste Agency (KORAD), Technology Development of Optimization for Spent Nuclear Fuel Storage and Transportation System, 2nd stage evaluation report (2014).
  3. American Society of Mechanical Engineers (ASME), Containment Systems and Transport Packagings for Spent Nuclear Fuel and High Level Radioactive Waste, ASME Boiler and Pressure Vessel Code Section III, Division 3 (2010).
  4. Electric Power Research Institute (EPRI), Qualification of METAMIC$^{(R)}$ for Spent-Fuel Storage Application, EPRI Technical Report 1003137 (2001).
  5. U.S. Nuclear Regulatory Commission (NRC), Cladding Considerations for the Transportation and Storage of Spent Fuel, Interim Staff Guidance-11, Revision 3 (2003).

Cited by

  1. Preliminary Design of the Forced Gas Drying System for Spent Nuclear Fuel Dry Storage vol.15, pp.4, 2017, https://doi.org/10.7733/jnfcwt.2017.15.4.403
  2. Review of Research on Chloride-Induced Stress Corrosion Cracking of Dry Storage Canisters in the United States vol.16, pp.4, 2018, https://doi.org/10.7733/jnfcwt.2018.16.4.455