경수로 사용후핵연료 건식저장용기 간 중성자 표면선속 간섭률 평가
Evaluation of Neutron Flux Accounting for Shadowing Effect Among the Dry Storage Casks
2
조회
0
다운로드
0
인용
0
참고문헌
키워드
초록
The Korean 2nd basic plan for management of high-level radioactive waste presented a plan to managespent nuclear fuel through dry storage facilities in NPP on-site. For the construction and operation of the facility, it isnecessary to develop the monitoring system of the integrity of spent nuclear fuel before operation. NUREG-1536 recommendsthat the theoretical cask array, typically in the 2×10 array, should account for shadowing effect among thedry storage casks. The objective of this study was to evaluate neutron flux accounting for shadowing effect among drystorage casks. The neutron release rate was evaluated using ORIGEN based on the design basis fuel condition. Andthe simulation of dry storage casks and evaluation of the shadowing effect were performed using MCNP. Shadowingeffect of other dry storage casks was the highest at the center of the dry storage facility of the 2 × 10 array comparedwith the outside of the cask. The shadowing effect of neutron flux on the surface among the metal casks was approximately18% at point 1, 23% at point 2, and 43% at point 3. For the concrete casks, the shadowing effect of neutronflux on the surface was approximately 46% at point 1, 51% at point 2, and 52% at point 3. This means that correctionis necessary to monitor the integrity of spent nuclear fuel in each dry storage cask through evaluation of shadowingeffect. The results of this study will be used for comparative analysis of neutron measurement data from spent nuclearfuels in dry storage cask. Additionally, the neutron flux evaluation procedure used in this study could be used as thebasic data of safety assessment of dry storage cask and development of safety guide.
Abstract
The Korean 2nd basic plan for management of high-level radioactive waste presented a plan to managespent nuclear fuel through dry storage facilities in NPP on-site. For the construction and operation of the facility, it isnecessary to develop the monitoring system of the integrity of spent nuclear fuel before operation. NUREG-1536 recommendsthat the theoretical cask array, typically in the 2×10 array, should account for shadowing effect among thedry storage casks. The objective of this study was to evaluate neutron flux accounting for shadowing effect among drystorage casks. The neutron release rate was evaluated using ORIGEN based on the design basis fuel condition. Andthe simulation of dry storage casks and evaluation of the shadowing effect were performed using MCNP. Shadowingeffect of other dry storage casks was the highest at the center of the dry storage facility of the 2 × 10 array comparedwith the outside of the cask. The shadowing effect of neutron flux on the surface among the metal casks was approximately18% at point 1, 23% at point 2, and 43% at point 3. For the concrete casks, the shadowing effect of neutronflux on the surface was approximately 46% at point 1, 51% at point 2, and 52% at point 3. This means that correctionis necessary to monitor the integrity of spent nuclear fuel in each dry storage cask through evaluation of shadowingeffect. The results of this study will be used for comparative analysis of neutron measurement data from spent nuclearfuels in dry storage cask. Additionally, the neutron flux evaluation procedure used in this study could be used as thebasic data of safety assessment of dry storage cask and development of safety guide.
참고문헌 (25)
- Korean 2nd Basic Plan for the Management of HLW, "MOTIE", ~ (2021)
- IAEA, "Storage of Spent Nuclear Fuel", IAEA Safety Standards Series No. SSG-15, ~ (2012)
- IAEA, "Development and Implementation Support Programme for Nuclear Verification 2022-2023", STR-400, ~ (2022)
- NRC, "Standard Review Plan for Spent Fuel Dry Storage Facilities", NUREG-1567, ~ (2000)
- NRC, "Recommendations for Shielding Evaluations for Transport and Storage Packages", NUREG, 2003
- NRC, "Standard Review Plan for Spent Fuel Dry Storage Systems at a General License Facility", NUREG-1536, ~ (2010)
- Chung HJ, "Spent Nuclear Fuel Cask and Storage Monitoring with 4He Scintillation Fast Neutron Detectors", Proceedings of the KNS 2014 Fall Meeting (2014)
- Kim TM, "Preliminary Assessment of Radiation Impact from Dry Storage Facilities for PWR Spent Fuel", J Radiat Prot, 37(4), pp.197~201 (2012)[DOI]
- Seo MH, "Preliminary Analysis of Dose Rate Variation on the Containment Building Wall of Dry Interim Storage Facilities for PWR Spent Nuclear Fuel", J Radiat Prot, 38(4), pp.189~193 (2013)[DOI]
- Ko JH, "Shielding Analysis of Dual Purpose Casks for Spent Nuclear Fuel Under Normal Storage Conditions", Nucl. Eng. Technol, 46(4), pp.547~556 (2014)[DOI]
- Kim TM, "Preliminary Shielding Analysis of the Concrete Cask for Spent Nuclear Fuel Under Dry Storage Conditions", J. Nucl. Fuel Cycle Waste Technol, 15(4), pp.391~402 (2017)[DOI]
- NRC, "Recommendations on Fuel Parameters for Standard Technical Specifications for Spent Fuel Storage Casks", NUREG, 2001
- Dho HS, "The Evaluation of Minimum Cooling Period for Loading of PWR Spent Nuclear Fuel of a Dual Purpose Metal Cask", J. Nucl. Fuel Cycle Waste Technol, 14(4), pp.411~422 (2016)[DOI]
- Gauld IC, "Origen-S: Scale System Module to Calculate Fuel Depletion, Actinide Transmutation, Fission Product Buildup and Decay, and Associated Radiation Source Terms", ORNL, 39, Version 6, Vol. II, Sect. F7, pp.2009, ~
- Bowman SM, "OrigenArp Primer: How to Perform Isotopic Depletion and Decay Calculations with SCALE", ORIGEN, TM-2010, pp.43, 2010[DOI]
- NRC, "Recommendations for Addressing Axial Burnup in PWR Burnup Credit Analyses", NUREG, 2003
- Pelowitz DB, "MCNPXTM User’s Manual", LA-CP-11-00438, ~ (2011)
- Shielding Safety Analysis Report of Concrete Storage Cask, "KORAD", ~, pp.14220-P1-N-TR-032 (2013)
- Topical Report of Dual Purpose Metal Cask, "KORAD", ~, pp.1731-P1-N-RP-003 (2016)
- KORAD, "Development of SNF Transportation and Storage Casks in Korea", The 3rd International Symposium on Safety Improvement & Stakeholder confidence in Radioactive Waste Management (2016)
- ICRP, "Nuclear Decay Data for Dosimetric Calculations", ICRP publication 107. Ann. ICRP 38 (3), ~ (2008)
- Cacciapouti RJ, "Axial Burnup Profile Database for Pressurized Water Reactors", YAEC-1937, ~ (1997)
- NRC, "Standard Review Plan for Transportation Packages for Spent Fuel and Radioactive Material", NUREG-2216, ~ (2020)
- A Study on the Characteristics of the Radiation Source Terms of Spent Fuel and Various Non-Fuel Hardware for Shielding Applications, "ORNL", ~, pp.ORNL (2023), SPR-2021[DOI]
- NRC, "Updated Recommendations Related to Spent Fuel Transport and Dry Storage Shielding Analyses", NUREG, 2024