• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.06a
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• pp.345-345
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• 2004

The spent fuel transportation casks have used as one of the most essential component in the nuclear industry. And, the number of the cask has been significantly increased in recent years. While the bulk amount of spent fuel in the world is still kept in the storage pool, the number of countries which have chosen the advantages of dual purpose cask for transportation and storage is rapidly increasing. The technical experience in the area of spent fuel transportation cask operation and maintenance for long period is also available and will be well utilized also in storage casks. The increasing use of casks for dual and multiple purposes raises an issue of long term consideration by international standardization. Accordingly IAEA is providing a regulatory requirements and guidelines as an effort for this standardization.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2016.10a
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• pp.105-106
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• 2016

• Nuclear Engineering and Technology
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• v.20 no.1
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• pp.27-34
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• 1988

Since the lack of the spent fuel storage capcity has been expected for all Korean nuclear power plants in the mid-1990s, the maximum density rack (MDR) with consolidated fuels can be proposed to overcome the shortage of the storage capacity in KNU 9 & 10 which have most limited capacities. To ensure the safety when the alternatives are applied in the KNU 9 & 10, the multiplication factor are calculated with varying the rack pitch and the thickness of consolidated storage box by the AMPX-KENO IV codes. The computing system is verified by the benchmark calculation with criticality experiments for arrays of consolidated fuel modules, which was reported by B & W in 1981. Also an abnormal condition, i.e. malposition accident, is simulated. The results indicate that the KNU 9 & 10 storage pools with consolidated fuel are safe in the view of the criticality. Thus the storage capacity can be expanded from 9/3 cores into 27/3 cores even with considering equipments and cooling spaces.

• Journal of Radiation Protection and Research
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• v.30 no.2
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• pp.61-67
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• 2005

The criticality analysis method using HELIOS-MASTER code system, which is the nuclear core analysis code system, was developed for the spent fuel storage of SMART-P reactor. We generated the macroscopic cross section of the geometric model with HELIOS and estimated the criticality of the 3-dimensional model with MASTER for SMART-P spent fuel storage. The validity of criticality analysis method for SMART-P spent fuel storage with the HELIOS-MASTER code system by 3-D MCNP calculation was also verified. The result of the criticality analysis with the HELIOS-MASTER code system is more conservative than that with the MCNP and the accuracy of this result is within the range of an allowable error. Because HELIOS-MASTER can perform the 3-D depletion calculation lot a spent fuel storage, it will be useful to perform the criticality analysis including a burnup credit in future.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2011.05a
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• pp.23-24
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• 2011

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2011.10a
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• pp.35-36
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• 2011

• The Journal of the Korea institute of electronic communication sciences
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• v.14 no.3
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• pp.505-512
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• 2019

We propose a new method to monitor the water level of spent fuel pool in a nuclear power plant without electric power. We also analyze the performance and limitation of the proposed method. Our method is based on the reflected optical power at the end of optical fiber through a $1{\times}N$ optical coupler. We reveal that there is no problem to monitor the water level when using a $1{\times}8$ optical coupler. However, when a $1{\times}16$ optical coupler is used, only 15 out of 16 output ports can be used due to Rayleigh back-scattering. When a $1{\times}32$ optical coupler is used, only 25 out of 32 output ports can be used to monitor the water level.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.4 no.1
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• pp.51-58
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• 2006

Since 2002, more than 400 PWR spent nuclear fuel assemblies have been transported and stored on-site using transport casks in order to secure the storage capacity of PWR spent nuclear fuel of Kori nuclear power plant. The complete on-site transport system, which includes KN-12 transport casks, the related equipment and transport vehicles, had been developed and provided. KN-12 transport casks were designed, fabricated and licensed in accordance with Korean and IAEA's transport regulations, and the related equipment was also provided in accordance with the related regulations. The on-site transport and storage operation using two KN-12 casks and the related equipment has been conducted, and the strict Quality Control and Radiation Safety Management through the whole process has been carried out so as to achieve the required safety and reliability of the on-site transport of spent nuclear fuel.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.16 no.4
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• pp.455-472
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• 2018

It is important to study how to manage dry storage casks of spent nuclear fuels (SNF), because wet storage spaces for SNF will shortly be at full capacity in the Republic of Korea. The US has operated a dry storage cask system for several decades, and has carried out significant studies into how to successfully manage dry storage cask for SNF. This type of expertise and experience is currently lacking in the Republic of Korea. The degradation of dry casks is an important issue that must be considered. In particular, chloride-induced stress corrosion cracking (CISCC) is known to lead to the release of radioisotopes from canisters. The U.S. Department of Energy, U.S. Nuclear Regulatory Commission, and the Electric Power Research Institute have undertaken research into the CISCC mechanism. In addition, Sandia National Laboratories (SNL) has extensively researched CISCC and how to manage it in dry storage canisters. In this review paper, the probabilistic model proposed by the SNL is analyzed and, based on this model, US-based CISCC research is reviewed in detail. This paper will inform the management of dry cask storage of SNF from light water reactors in austenite stainless steel canisters in the Republic of Korea.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2015.10a
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• pp.115-116
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• 2015