• Nuclear Engineering and Technology
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• v.54 no.2
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• pp.637-643
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• 2022

Uranium and plutonium are required to be accounted in spent fuel head-end and major recovery area in pyro-process for safeguards purpose. The possibility of neutron resonance technique, as a nondestructive analysis, was simulated on isotopic fissile analysis for large scale process. Neutron resonance technique has advantage to distinguish uranium from plutonium directly in mixture. Simulation was performed on U235 and Pu239 assay in spent fuel and for scoping examination of assembly type. The resonance energies were determined for U235 and Pu239. The linearity in the neutron transmission was examined for the selected resonance energies. In addition, the limit for detection was examined by changing sample density, thickness and content for actual application. Several factors were proposed for neutron production and the moderated neutron source was simulated for effective and efficient transmission measurement. From the simulation results, neutron resonance technique is promising to analyze U235 and Pu239 for spent fuel assembly. An accurate fissile assay will contribute to an increased safeguards for the pyro-processing system and international credibility on the reuse of fissile materials in the fuel cycle.

• Journal of the Korean Society of Radiology
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• v.17 no.7
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• pp.1189-1195
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• 2023

In scenarios involving inspections and verifications of nuclear facilities, ensuring the proper functioning of on-site safeguards equipment is crucial. There have been precedents in Kazakhstan where equipment failed to operate properly due to extremly cold temperatures, and the year-round minimum temperature at North Korea's Punggye-ri nuclear test site is approximately minus 30 degrees Celsius. To ensure the proper functioning of equipment in extreme environments for on-site verification of nuclear activities on the Korean Peninsula, relevant research is necessary. This includes confirming the functionality of equipment used in inspections and verifications, as well as analyzing factors that may disrupt their normal operation. This study aims to conduct a risk analysis for the normal operation of equipment in extreme environments and develop criteria and procedures for environmental-based performance testing. To achieve this, we conducted a risk analysis based on IAEA safeguards, analyzed the utilization of equipment, and performed a risk analysis associated with transportation for on-site verification considering the environmental characteristics of the Korean Peninsula. Furthermore, we provided performance testing criteria and procedures. The research results can be utilized as reference material in the verification and monitoring processes of nuclear activities.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2018.11a
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• pp.51-52
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• 2018

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2018.05a
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• pp.23-24
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• 2018

• Nuclear Engineering and Technology
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• v.48 no.2
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• pp.285-292
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• 2016

Reactor neutrinos have been detected in the past 50 years by various detectors for different purposes. Beginning in the 1980s, neutrino physicists have tried to use neutrinos to monitor reactors and develop an optimized detector for nuclear safeguards. Recently, motivated by neutrino oscillation physics, the technology and scale of reactor neutrino detection have progressed considerably. In this review, I will give an overview of the detection technology for reactor neutrinos, and describe the issues related to further improvements in optimized detectors for reactor monitoring.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2018.11a
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• pp.39-40
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• 2018

• Proceedings of the Korean Nuclear Society Conference
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• 2004.10a
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• pp.1447-1448
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• 2004

As the plants are classified as a bulk facility by the Agency's safeguards criteria, the Material Balance Evaluation is a good tool to timely detect diversion that will be accomplished through the creation of defects as small as bias defects. Through all evaluations made by the Agency, it Is strongly recommended to report SRD based on both weight and enrichment, maintain the reliable MUF declaration and improve the gamma spectrometry measurement procedure. These recommendations have been now applied and are going on.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.406-410
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• 2003

DUPIC Fuel Development Facility(DFDF) is the facility to fabricate CANDU-type fuel from spent PWR fuel material without any separation of fissile elements and fission products. Unattended continuous surveillance systems for safeguards of nuclear facility result in large amounts of image and radiation data, which require much time and effort to inspect. Therefore, it is necessary to develop system that automatically pinpoints and diagnoses the anomalies from data. In this regards, this paper presents a novel concept of the continuous surveillance system that integrates visual image and radiation data by the use of neural networks. This surveillance system is operating for safeguards of the DFDF in KAERI.

• Nuclear Engineering and Technology
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• v.27 no.3
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• pp.447-452
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• 1995

경·중수로 연계 핵연료 주기 (Direct Use of Spent PWR Fuel in CANDU : DUPIC ) 기술개발의 핵물질 보장조치(Safeguards)는 경수로 사용후 핵연료를 중수로에 재 활용하기 위한 DUPIC 공정에 대한 최적 보장조치 시스템을 구축하여, 국제 원자력 기구(IAEA) 및 국제 원자력 사회에서 핵 투명성확보 및 신뢰도를 향상시키는 것을 기술개발의 목적으로 하고 있다. DUPIC 공정은 고립된 차폐시설내의 고준위 방사선장 하에서 가동되므로 타 시설에 비해 핵 물질 전용 가능성은 희박하지만, 전 공정이 원격제어 되야 하고, 조업조건이 정복해야 하므로 기존의 보장조치 기술보다 더욱 발전된 계량관리시스템, 측정시스템 및 감시시스템 등을 개발하여야 한다. 이를 위해 본 연구에서는 각 항목에 대한 요소 분석 및 각 항목별 향후 연구방향에 대해 분석하였다. DUPIC 공정 전반에 대한 핵물질 계량관리를 위해 물질수지구역 (Material Balance Area : MBA) 및 주요측정 지점 (Key Measurement Point : KMP )을 설정하여 각 측정지점별 측정방법 및 재고검증(Inventory Verification) 방법을 분석하였다. 최적 측정시스템을 개발하기 위해 적용 가능한 비파괴분석 방법들을 분석한 결과, 핵분열성 물질 함량을 정량적으로 측정할 수 있는 수동적 중성자 측정법이 가장 적합하다는 결론을 얻었다. 또한, 감시시스템을 개발하기 위해 전용전략의 주요 요소 및 전용경로 등을 분석하였으며, 핵물질 및 시설에 대한 물리적 방호체제를 DUPIC시설에 적용하기 위하여 물리적 방호에 필요한 방호체제 요소를 분석하여 DUPIC 시설을 위한 가상적인 방호체제를 구축하였다.

• Nuclear Engineering and Technology
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• v.39 no.6
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• pp.691-696
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• 2007

Nuclear energy programs around the world increasingly find themselves at the nexus of potentially conflicting demands from both domestic and international stakeholders. On one side, the rapid growth in demand for electricity coupled with the goal of reducing carbon emissions calls for a significant expansion of nuclear energy. On the other, stakeholders are seeking ever greater safety, environmental, security, and nonproliferation assurances before consenting to the construction of new nuclear energy facilities. Satisfying the demand for clean energy supplies will require nuclear energy operators to find new and innovative ways to build confidence among stakeholders. This paper discusses two related concepts which can contribute to meeting the needs of key stakeholders in cost effective and efficient ways. Structured processes and tools for assessing stakeholder needs can build trust and confidence while facilitating the "designing-in" of information collection systems for new facilities to achieve maximum efficiency and effectiveness. Integrated approaches to monitoring facilities and managing the resulting data can provide stakeholders with continued confidence while offering operators additional facility and process information to improve performance.