• Nuclear Engineering and Technology
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• 제56권2호
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• pp.728-744
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• 2024

The presence of hydrogen absorbed by zirconium-based cladding materials during reactor operation can trigger degradation mechanisms and endanger the rod integrity. Ensuring the durability of the rods in extended time-frames like dry storage requires anticipating hydrogen behavior using numerical modeling. In this context, the present paper describes a hydrogen post-processing tool for Falcon - HYPE, a PSI's in-house tool able to calculate hydrogen uptake, transport, thermochemistry, reorientation of hydrides and hydrogen-related failure criteria. The tool extracts all necessary data from a Falcon output file; therefore, it can be considered loosely coupled to Falcon. HYPE has been successfully validated against experimental data and applied to reactor operation and interim storage scenarios to present its capabilities.

• Nuclear Engineering and Technology
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• 제53권6호
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• pp.1869-1877
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• 2021

This paper presents the neutron dose rate analysis of the new CONSTOR® RBMK-1500/M2 storage cask intended for the spent nuclear fuel storage at Ignalina Nuclear Power Plant in Lithuania. These casks are designed to be stored in a new "closed" type interim storage facility, with the capacity to store up to 202 CONSTOR® RBMK-1500/M2 casks. In 2016 y, the "hot trials" of this new facility were conducted and 10 CONSTOR® RBMK-1500/M2 casks loaded with the spent nuclear fuel were transported to the dedicated storage places in this facility. During "hot trials", the dose rate measurements of the CONSTOR® RBMK-1500/M2 casks were performed as the dose rate is one of the critical parameter to control and it must be below design (and safety) criteria. Therefore, having the actual data of the spent nuclear fuel characteristics, the neutron dose rate modeling of the CONSTOR® RBMK-1500/M2 cask loaded with this particular fuel was also performed. Neutron dose rate modeling was performed using MCNP 5 computer code with very detailed geometrical representation of the cask and the fuel. The obtained modeling results were compared with the measurement results and it was revealed, that modeling results are generally in good agreement with the measurements.

• 방사성폐기물학회지
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• 제21권4호
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• pp.531-541
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• 2023

The Wolsong Nuclear Power Plant (NPP) operates an on-site spent fuel dry storage facility using concrete silo and vertical module systems. This facility must be safely maintained until the spent nuclear fuel (SNF) is transferred to an external interim or final disposal facility, aligning with national policies on spent nuclear fuel management. The concrete silo system, operational since 1992, requires an aging management review for its long-term operation and potential license renewal. This involves comparing aging management programs of different dry storage systems against the U.S. NRC's guidelines for license renewal of spent nuclear fuel dry storage facilities and the U.S. DOE's program for long-term storage. Based on this comparison, a specific aging management program for the silo system was developed. Furthermore, the facility's current practices-periodic checks of surface dose rate, contamination, weld integrity, leakage, surface and groundwater, cumulative dose, and concrete structure-were evaluated for their suitability in managing the silo system's aging. Based on this review, several improvements were proposed.

• 환경영향평가
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• 제18권6호
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• pp.359-366
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• 2009

CCS (Carbon Capture and Storage) is considered as the most promising interim solution to deal with the greenhouse gas such as $CO_2$ responsible for global warming. Even though carefully chosen geologic formations are known to contain stored gas for a long time period, there are potential risks of leakage. Up to now, applicable risk assessment procedures for the leakage of $CO_2$ are not available. This study presents a basis for risk analysis applicable to a complex geologic storage system. It starts with the classification of potential leakage pathways. Receptors and the leakage effect on them are identified and quantified. Then, a fault tree is constructed, which yields the minimum cut set (i.e., the most vulnerable leakage pathway) and quantifies the probability of the leakage risk through the cut set. The methodology will provide a tool for risk assessment in a CCS project. The outcomes of the assessment will not only ensure the safety of the CCS system but also offer a reliable and efficient monitoring plan.

• Nuclear Engineering and Technology
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• 제21권3호
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• pp.223-230
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• 1989

본 연구는 이산 모형으로 표현되는 사용후 핵연료 중간 저장 공정을 전산기 모사하였다. 이는 계통 흐름을 보여주며, 기기 성능을 평가하고 계통 구성 요소와 흐름을 확립하여 설계에 관한 계통 구성 및 운전지침에 대한 정보를 제공한다. 공정 모사를 통하여 가장 좋은 시스템을 구성하기 위하여 주요 변수에 대하여 시험 분석하였다. 전산기 모사 결과에 의하면 하루 2교대 및 2대의 냉각 시설이 최적안으로 나타났다. 이산 공정 모사는 저장 시설의 최적 설계와 운전 자료를 얻는데 효과적으로 사용될 수 있다.

• Nuclear Engineering and Technology
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• 제55권11호
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• pp.4125-4133
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• 2023

The transportation of spent nuclear fuel is an important process that involves road and sea transport from an interim storage facility to storage and final disposal sites. As spent nuclear fuel poses a significant risk, carefully evaluating its vibration and shock characteristics under normal transport conditions is essential. In this regard, full-scale multi-modal transport tests (MMTT) have been conducted domestically and internationally. In this paper, we discuss the process of developing a multi-body dynamics (MBD) model to analytically simulate conditions that cannot be considered in tests. The MBD model is based on the KORAD-21 transportation system was validated using the Korean MMTT results from 2020 to 2021. This paper summarizes the details of the development and verification of the MBD model for the KORAD-21 transportation system under normal transport test conditions. This approach can be applicable to various transportation scenarios and systems, and the results of this study will help to ensure that nuclear fuel transportation is conducted safely and effectively.

• 방사성폐기물학회지
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• 제13권4호
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• pp.301-313
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• 2015

사용후핵연료 건식저장을 위한 지상저장 기술 및 동굴저장 기술의 현황을 살펴보고, 동굴저장 기술을 이용한 사용후핵연료 건식저장의 국내 적용 가능성을 분석하였다. 사용후핵연료 건식저장을 위한 동굴저장 기술의 타당성, 경제성 및 기술적 측면을 검토하였다. 지상 건식저장시설을 건설하기 위해서는 외부로부터 격리되어 있는 상당한 면적의 평탄한 부지가 필요하나, 산악지형이 주를 이루는 우리나라의 실정에서, 이러한 부지를 확보하는 것이 쉽지 않을 수도 있다. 만일 산지의 동굴 내에 사용후핵연료 저장시설을 건설한다면, 이러한 부지 문제를 보다 쉽게 해결할 수 있다. 따라서 동굴저장 방식은 자연 및 사회적 환경을 고려할 때, 우리나라의 사용후핵연료 건식저장을 위한 유력한 대안이 될 수 있다. 사용후핵연료 동굴저장 방식은 지상 건식저장 기술에 비해 여러 가지 장점을 가지고 있으며, 경제성 측면에서도 큰 차이가 없다. 또 동굴저장 방식을 국내의 사용후핵연료 건식저장에 적용하는 데 큰 기술적인 장벽은 없다.

• Journal of Radiation Protection and Research
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• 제21권4호
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• pp.313-327
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• 1996

원전부지내(AR) 사용후핵연료 건식저장방식으로 횡형콘크리트 모듈방식, 금속 저장용기 방식, 콘크리트 저장용기 방식, 수송저장 겸용용기 방식 및 다목적용기 방식 등이 있다. 이중다목적용기 방식을 제외한 다른 방식들은 각각 운영인허가를 받아 이미 세계 각 국에서 사용후핵연료 AR 건식저장에 사용되고 있으며 다목적용기 방식도 최근 개발을 활발히 진행하고 있는 상태이다. AR 건식저장 시설을 운영하고 있거나 추진중인 나라는 미국, 일본, 독일, 캐나다, 스페인, 체코, 스위스 등으로 AR 건식저장을 거쳐 중간저장이나 재처리시설로 수송하는 방식을 채택하고 있다. 우리나라의 경우 월성에서 콘크리트 Silo 건식저장을 이미 사용하고 있으며 일부 다른 원자로도 사용후핵연료 저장능력이 한계에 도달하고 있는 현실을 감안할 때 AR 임시 저장은 불가피한 것으로 여겨진다. 본 보고서에서는 고리를 비롯한 국내원전에 적용 가능한 외국의 AR 저장 시스템 각각에 대하여 설계특성, 설계요건, 기술기준 및 현황 등을 논의하였다. 대부분의 경우 저장용기 인허가 기간은 20년으로 제한하고 있으며 전 수명기간동안 재질의 건전성, 밀봉유지 등이 중요하게 요구되고 있다.

• Nuclear Engineering and Technology
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• 제46권1호
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• pp.73-80
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• 2014

A concrete cask is an option for spent nuclear fuel interim storage. A concrete cask usually consists of a metallic canister which confines the spent nuclear fuel assemblies and a concrete overpack. When the overpack undergoes a missile impact, which might be caused by a tornado or an aircraft crash, it should sustain an acceptable level of structural integrity so that its radiation shielding capability and the retrievability of the canister are maintained. A missile impact against a concrete overpack produces two damage modes, local damage and global damage. In conventional approaches [1], those two damage modes are decoupled and evaluated separately. The local damage of concrete is usually evaluated by empirical formulas, while the global damage is evaluated by finite element analysis. However, this decoupled approach may lead to a very conservative estimation of both damages. In this research, finite element analysis with material failure models and element erosion is applied to the evaluation of local and global damage of concrete overpacks under high speed missile impacts. Two types of concrete overpacks with different configurations are considered. The numerical simulation results are compared with test results, and it is shown that the finite element analysis predicts both local and global damage qualitatively well, but the quantitative accuracy of the results are highly dependent on the fine-tuning of material and failure parameters.

• International Journal of Computer Science & Network Security
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• 제24권5호
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• pp.95-102
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• 2024

In distributed computing, accessible encryption strategy over Auditable data is a hot research field. Be that as it may, most existing system on encoded look and auditable over outsourced cloud information and disregard customized seek goal. Distributed storage space get to manage is imperative for the security of given information, where information security is executed just for the encoded content. It is a smaller amount secure in light of the fact that the Intruder has been endeavored to separate the scrambled records or Information. To determine this issue we have actualize (CBC) figure piece fastening. It is tied in with adding XOR each plaintext piece to the figure content square that was already delivered. We propose a novel heterogeneous structure to evaluate the issue of single-point execution bottleneck and give a more proficient access control plot with a reviewing component. In the interim, in our plan, a CA (Central Authority) is acquainted with create mystery keys for authenticity confirmed clients. Not at all like other multi specialist get to control plots, each of the experts in our plan deals with the entire trait set independently. Keywords: Cloud storage, Access control, Auditing, CBC.