Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT) (방사성폐기물학회지)

Korean Radioactive Waste Society (한국방사성폐기물학회)
권호 표지
DOI QR코드

DOI QR Code

Status Analysis for the Confinement Monitoring Technology of PWR Spent Nuclear Fuel Dry Storage System

경수로 사용후핵연료 건식저장시스템의 격납감시 기술현황 분석

  • Received : 2015.09.24
  • Accepted : 2015.12.04
  • Published : 2016.03.30
Download PDF
⟨ Previous Next ⟩

Abstract

Leading national R&D project to design a PWR spent nuclear fuel interim dry storage system that has been under development since mid-2009, which consists of a dual purpose metal cask and concrete storage cask. To ensure the safe operation of dry storage systems in foreign countries, major confinement monitoring techniques currently consist of pressure and temperature measurement. In the case of a dual purpose metal cask, a pressure sensor is installed in the interspace of bolted double lid(primary and secondary lid) in order to measure pressure. A concrete storage cask is a canister based system made of double/redundant welded lid to ensure confinement integrity. For this reason, confinement monitoring method is real time temperature measurement by thermocouple placed in the air flow(air intake and exit) of the concrete structure(over pack and module). The use of various monitoring technologies and operating experiences for the interim dry storage system over the last decades in foreign countries were analyzed. On the basis of the analysis above, development of the confinement monitoring technology that can be used optimally in our system will be available in the near future.

Keywords

References

  1. International Atomic Energy Agency, Storage of Spent Nuclear Fuel, IAEA SAFETY STANDARDS SERIES No. SSG-15, IAEA (2012).
  2. United States Nuclear Regulatory Commission, Licensing Requirements for the Independent Storage of Spent Nuclear Fuel, High-Level Radioactive Waste and Reactor Related Greater than Class C Waste, U.S. NRC 10CFR72 (2012).
  3. International Atomic Energy Agency, Guidance for preparation of a safety case for a dual purpose cask containing spent fuel, 43-49, IAEA-TECDOC-DRAFT, IAEA (2013).
  4. United States Nuclear Regulatory Commission, Standard Review Plan for Dry Cask Storage Systems, Revision 1, U.S. NRC NUREG-1536 (2010).
  5. J.D. Lambert, S. Bakhtiari, I. Bodnar, C. Kot, and J. Pence, NRC Job Code V6060: Extended In-Situ and Real Time Monitoring Task 3: Long-Term Dry Cask Storage of Spent Nuclear Fuel, v-vii, 17-18, Argonne National Laboratory (2012).
  6. United States Nuclear Regulatory Commission , "Available methods for functional monitoring of dry cask storage systems", 1-1-1-5, U.S. NRC Contract NRC-HQ-12-C-02-0089, (2014).
  7. T. Ishikawa, "Current Status of Interim Storage Facility for Spent Fuels in Japan", Cask Procurement Group, Engineering Department, Recyclable Fuel Storage Company, IAEA workshop for DPC, 8 (2014).
  8. L. Oelschlager, W. Graf, and M. Heck, "GNS Experience on the Long-Term Storage at Dry Interim Storage Facilities Especially in Ahaus and Gorleben(GNS, Germany)", OECD/NEA International workshop, 383-395, May 21-23, 2013, Munich.
  9. H. Volzke, "Dry Spent Fuel Storage in Dual Purpose Casks(Aging Management Issues)", INMM Spent Fuel Management Seminar XXVIII, 13-14, January 14-16, 2013, Arlington, VA.
  10. S. Kuba, "Operational Experience of Castor 440/84 Casks in Dukovany NPP", CEZ plc Nuclear Power Division, Prague, Czech Republic, PATRAM, Berlin, Germany (2004).

Cited by

  1. 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