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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2017.1
- 수록면
- 1,563 - 1,570 (8page)
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In order to perform dry interim storage and transportation of the spent-fuel assemblies of the BushehrNuclear Power Plant, dual-purpose casks can be utilized. The effectiveness of different neutron-shieldmaterials for the dual-purpose cask was analyzed through a set of calculations carried out using theMonte Carlo N-Particle (MCNP) code. The dose rate for the dual-purpose cask utilizing the recentlydeveloped materials of epoxy/clay/B4C and epoxy/clay/B4C/carbon fiber was less than the allowableradiation level of 2 mSv/h at any point and 0.1 mSv/h at 2 m from the external surface of the cask. Byutilization of epoxy/clay/B4C instead of an ethylene glycol/water mixture, the dose rates on the sidesurface of the cask due to neutron sources and consequent secondary gamma rays will be reduced by17.5% and 10%, respectively. The overall dose rate in this case will be reduced by 11%.
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참고문헌 (24)
참고문헌 신청
A. M. Kirkin / 2015 / Implementation of guidance for an integrated transport and storage safety case for dual purpose casks for spent nuclear fuel in Russian regulatory document /
B. Droste / 2014 / Overview of preparation of a safety case for a dual purpose cask for storage and transport of spent fuel and recommendations to WASSC and TRANSSC from WASSC/TRA
Chang Je Park / 2008 / SHIELDING PERFORMANCE OF A NEWLY DESIGNED TRANSPORT CASK IN THE ADVANCED CONDITIONING SPENT FUEL PYROPROCESS FACILITIY / Nuclear Engineering and Techn
Design and Engineering Survey Institute / 2003 / Safety Analysis Report for the Bushehr Nuclear Power Plant
I. I. Linge / 2012 / End-to-end calculation of the radiation characteristics of VVER-1000 spent fuel assemblies / Phys. At. Nucl 75 : 1603 ~ 1615
B. Droste / 2014 / Overview of preparation of a safety case for a dual purpose cask for storage and transport of spent fuel and recommendations to WASSC and TRANSSC from WASSC/TRA
Chang Je Park / 2008 / SHIELDING PERFORMANCE OF A NEWLY DESIGNED TRANSPORT CASK IN THE ADVANCED CONDITIONING SPENT FUEL PYROPROCESS FACILITIY / Nuclear Engineering and Techn
Design and Engineering Survey Institute / 2003 / Safety Analysis Report for the Bushehr Nuclear Power Plant
I. I. Linge / 2012 / End-to-end calculation of the radiation characteristics of VVER-1000 spent fuel assemblies / Phys. At. Nucl 75 : 1603 ~ 1615
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