• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.16 no.4
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• pp.441-454
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• 2018

Since the permanent shutdown of Kori Unit 1 in 2017, a full-scale decommissioning project for a commercial nuclear reactor has been approaching. It is estimated that about 160,000 t of low-activity concrete waste will be produced from decommissioning of one unit of this commercial nuclear power reactor. Accordingly, it is necessary to review whether the effectiveness of the current regulatory framework for clearance waste (i.e. waste stream that meets activity concentration guidelines or dose criteria for clearance set forth in NSSC Notice No. 2017-65) can be maintained for the clearance of a bulk amount of concrete waste. In this regard, the IAEA SRS No. 44, which was used as a basis for revision of the Korean clearance regulations, is thoroughly analyzed and the radiological effects from four different clearance scenarios, along with input values and parameters derived from industrial practices in Korea, were evaluated. Though it is shown that the maximum annual dose from most recycling scenarios will be less than the clearance dose criterion for the normal scenario (i.e. an order of magnitude of $0.01mSv{\cdot}y^{-1}$), the radiation dose, estimated with conservative assumptions for the banking scenario, may exceed the above clearance dose criteria. Therefore, for safe and sustainable clearance of the bulk amount of concrete waste, it is required to diversify the concrete waste processors, perform more detailed site-specific assessment, and apply limiting conditions to the banking scenario.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.5 no.4
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• pp.297-308
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• 2007

The granulation equipment of concentrated wastes is manufactured for the polymer solidification of concentrated wastes. It uses liquid sodium silicate as a granulating agent for the granulating of dried powder containing boric acid. The granulating agent is sprayed in the form of droplet and mean size of dried granules is $2{\sim}4mm$. The new technology which has been used for the polymer solidification of spent resin in U.S. and certified by Nuclear Regulatory Commission (NRC) is successfully applied to concentrated wastes. This uses in-situ solidification process within drum without mechanical mixing. Maximum loading of waste can be achieved without increasing of waste volume. Polymer waste forms were evaluated with several test such as fire test, compressive strength test, leaching test, immersion test, irradiation test, and thermal cycling test according to standard test procedures.

• Journal of the Korean Society for Nondestructive Testing
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• v.19 no.4
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• pp.300-313
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• 1999

비파괴검사 기술의 레벨 향상과 안정화를 통한 시간적 재현성이 있는 비파괴검사 결과의 확보를 위해서는 비파괴검사 기술자의 자격 인정 및 인증(nondestructive testing qualification and certification of personnel)제도의 확립이 매우 중요하다. 비파괴검사 결과에 대한 유효성은 비파괴검사을 실시하는 사람의 능력이나 비파괴검사에 대한 책임을 지고 있는 사람의 능력에 크게 의존한다. 1974년부터 원자력 선진국들이 중심이 되어 수행된 PISC 프로그램(program for inspection of steel components) 및 EPRI 등에서는 순회시험 (piping inspection round-robin: PIRR trial) 결과 기존 비파괴검사 방법은 모의 시험편에 있는 상당히 큰 결함도 탐지하지 못하거나 정확한 결함크기를 측정하는데 실패한 경우가 있으며, 검사자의 기량 또는 신체조건에 상당한 차이가 있는 것으로 나타났다[1]. 국제표준화기구(ISO)의 비파괴검사 기술자의 기량인정 및 인증에 대한 국제규격안 DIS(draft international standard) 9712에서는 비파괴검사를 기획 실시 감독 감시 평가를 하기 위한 적절한 이론적 및 실무적 지식을 필요로 하는 기술자의 능력을 평가하고, 문서화하는 방법을 제공하는 절차를 제시하고 있다. 국제표준화기구에 의한 비파괴검사 기술자의 기량인정 및 인증에 대한 국제통합을 추진하는 동기는 제 3자에 의한 체계적인 인증시스템을 가지고 있지 않은 나라와 새로운 NDT 방법에 대해서 인증제도를 적용할 때 세계적인 공통성을 갖도록 유도하기 위함이다. 현재, 우리나라 비파괴검사 기술자의 기술자격 인증제도는 국가기술자격법에 의거하여 한국산업인력공단에서 주관하여 기술사, 기사, 산업기사, 기능사로 구분하여 실시하고 있다. 국제표준화기구의 비파괴검사 기술자의 자격과 인증에 대한 국제 통합화(안)[2]이 거의 마무리 단계에 있고 일본을 비롯한 많은 나라가 국제규격을 기초로 한 새로운 인증제도를 발족시켜 거의 시행 단계에 있다. 반면 국내에서는 한국비파괴검사학회(KSNT)에서 비파괴검사 기술자의 자격인정 및 인증제도의 개선방향이 제시된 바 있고 [3], 표준화위원회에서 나름대로 준비를 하고 있으나 아직 구체적인 실천단계에와 있지 못하다. 본 고에서는 최근 대폭수정 보완된 ISO/DIS 9712 국제규격(안)을 회원들에게 소개하고, 우리나라의 향후 대응방안에 관한 회원 여러분의 의견 수렴에 도움을 주고자 ISO/DIS 9712(1997)를 번역하여 제공한다.

• Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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• 2013.04a
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• pp.589-595
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• 2013

A reactor vessel internals comprehensive vibration assessment program(RVI CVAP) of an advanced power reactor 1400(APR1400) is being verified on the integrity of RVI for the design life of the plant by performing the non-prototype category-2 type on the US Nuclear Regulatory Commission Guide(NRC RG) 1.20, for which consists of a vibration and stress analysis program, a limited vibration measurement program, an inspection program, and the correlation of these programs. The aim of this paper is to describe the plan for the vibration measurement, test and acceptance criteria portion, and documentation and results of the APR1400 RVI CVAP. We will conduct the limited vibration measurement program of the APR1400 RVI CVAP according to the measurement plan and the vibration measurement testing in this paper.

• Transactions of the KSME C: Technology and Education
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• v.5 no.2
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• pp.127-134
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• 2017

The reactor internals shall be secured in safety and structural integrity under various vibrational loading conditions. Thus, U.S. NRC, Regulatory Guide 1.20 requires the evaluation for the reactor internals due to acoustic induced vibration including the response to the reactor coolant pump pressure pulsation. This paper suggests a methodology to develop an analytical model of the core support barrel accounting for the fluid around the structure and to analyze the responses to the pump pulsation loads using acoustic structure interaction analysis. The analysis results were compared with those of US Palo Verde 1 CVAP and showed a good agreement. Thus, it is expected that the suggested methodology could be an efficient way to evaluate the response of the core support barrel to the pump pulsation loads.

• Journal of Radiation Protection and Research
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• v.39 no.3
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• pp.150-158
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• 2014

Radiation-related practitioners and radiation-treated patients at medical institutions are inevitably exposed to radiation for diagnosis and treatment. Although standards for maximum doses are recommended by the International Commission on Radiological Protection (ICPR) and the International Atomic Energy Agency (IAEA), more direct and available measurement and analytical methods are necessary for optimal exposure management for potential exposure subjects such as practitioners and patients. Thus, in this study we developed a system for real-time radiation monitoring at a distance that works with existing portable device. The monitoring system comprises three parts for detection, imaging, and transmission. For miniaturization of the detection part, a scintillation detector was designed based on a silicon photomultiplier (SiPM). The imaging part uses a wireless charge-coupled device (CCD) camera module along with the detection part to transmit a radiation image and measured data through the transmission part using a Bluetooth-enabled portable device. To evaluate the performance of the developed system, diagnostic X-ray generators and sources of $^{137}Cs$, $^{22}Na$, $^{60}Co$, $^{204}Tl$, and $^{90}Sr$ were used. We checked the results for reactivity to gamma, beta, and X-ray radiation and determined that the error range in the response linearity is less than 3% with regard to radiation strength and in the detection accuracy evaluation with regard to measured distance using MCNPX Code. We hope that the results of this study will contribute to cost savings for radiation detection system configuration and to individual exposure management.

• Korean Security Journal
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• no.59
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• pp.217-242
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• 2019

Nowadays, Terrorism has become bloodier. Unlike the past, the recent terrorism has been indiscriminate in the purpose of mass- killing. Given this aspect, the threat of a CBRN attack is the biggest one to modern society. Notably, the possibility of terrorist attacks in Korea by international terrorist groups such as ISIL is higher than ever in consideration of its allusion; crusades and the devil's allied forces. To overcome these circumstances, various measures have been taken for counter terrorism at the state level including anti-terrorist legislation. Under the anti-terrorist act, police have to lead relevant inter agencies when it comes to the CBRN terror. At first glance, current countermeasures would work well. However, in order to respond quickly, the standing cooperations system of related departments need to be set up. In this sense, this article proposed a coagulatory body that could not only consider institutional-oriented organizational restructuring and response but also integrate and operate functions of various specialized institutions. It also stressed that the council should move toward a consultative body of information gathering, distribution and working- level consultation. With this cooperation system, counter-terrorism agencies can respond rapidly, stop wasting their effort and assets by about 30%. Also, they could design the atypical aspect of terrorism into standardized.

• Journal of Arbitration Studies
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• v.18 no.2
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• pp.201-233
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• 2008

러시아와 한국간의 공식적인 접촉은 1990년 6월 샌프란시스코에서 개최된 정상회담이다. 동년 9월 뉴욕에서 개최된 양국의 외무장관 회담에서 러시아와 한국의 외교관계가 수립되었다. 그간 양국간에는 협정을 통한 협력의 법적기반이 조성되었는데 주요 분야를 보면 무역, 투자보장, 어업, 이중과세방지, 군사기술분야, 원자력의 평화적 이용, 문화교류에 관한 협정들이 있다. 역시 양국간의 주요 관심사항은 무역과 경제협력 분야이다. 2007년도 러시아와 한국의 무역액은 150억 달러를 초과함으로써 전년도에 비해 55.5% 증가하였다. 러시아의 한국으로의 수출은 약 70억 달러로서 전년도에 비해 52.6% 증가했고 한국으로부터의 수입은 80억 달러를 초과함으로써 전년도에 비해 56.1% 증가하였다. 그리하여 러시아는 한국의 10대 교역국으로 성장하였다. 가스와 오일 프로젝트 추진과 관련하여 사할린지역에서 사용하기 위해 한국으로부터 수입하는 드릴기계장비, 탱커, 자동차, 휴대전화는 한국과 러시아 양국간 경제성장의 주요요인이 되고 있다. 2008년 1/4 분기 양국간 무역액은 42억 달러를 초과했는데 이는 전년도 동기와 비교해서 72.1% 증가한 것이다. 이 중 한국에의 수출은 17억 달러를 초과했는데 이는 전년도 1/4분기에 비해 91.7% 성장한 것이다. 한국으로부터의 수입은 약 25억 달러로서 전년도 1/4 분기와 대비해서 60.6% 성장했다. 러시아와 한국간의 경제교류가 크게 증대하게 된 배경에는 러-한경제과학기술협력공동위원회가 큰 역할을 담당했다. 이 논문에서 필자는 무역과 투자측면에서 본 양국간 경제협력의 특징을 고찰하는 한편 러시아의 동부지역(러시아 극동 및 바이칼횡단지역)과 한국과의 협력과 관련된 역동성과 과제를 제시하는데 연구의 목적을 두었다. 한국은 외국기업과 함께 러시아 극동지역의 무역과 경제협력 증진에 상당한 공헌을 함으로써 러시아 극동경제권에서 주요 무역파트너가 되고 있다. 또한 본 연구에서는 한국과 러시아간의 주요 협력프로젝트에 관하여 고찰하는 한편 앞으로의 전망을 제시하였다. 이 문제는 무엇보다도 한-러간의 공동 에너지프로젝트 및 에너지자원의 무역과 관련되어 있다. 한국과 러시아는 이미 많은 분야에서 상당한 정도로 상호 협력관계를 발전시켜왔다. 여기에는 정책, 에너지, 경제, 문화, 과학기술 분야가 포함되어 있다. 현재 러시아와 한국간에는 에너지 분야에서의 전략적 대화채널 구축에 관한 문제와 함께 연료 및 에너지공단 건설과 관련하여 협력문제가 논의되고 있다. 에너지 분야에서의 전략적 대화개념 구축을 위해서는 전략, 예측 및 투자환경의 문제가 양국간에 집중논의 되어야 하고 법제상의 조화문제도 논의되어야 한다.

• Journal of radiological science and technology
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• v.33 no.3
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• pp.269-276
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• 2010

This study attempts to propose ways to optimize and improve the period of hospitalization for the radioiodine treatment by calculating the dose rate of patients treated with high-dose radioiodine by distance and time slot. As a result, 24 hours after the patient was treated with 100 mCi high-dose iodine, the dose rate was attenuated to $1,035{\mu}Sv/hr$ at the navel, to $109{\mu}Sv/hr$ at 50 cm, and to $33{\mu}Sv/hr$ at 100 cm. 24 hours after the patient was treated with 150 mCi high-dose iodine, the dose rate was attenuated to $637{\mu}Sv/hr$ at the navel, to $100{\mu}Sv/hr$ at 50 cm, and to $40{\mu}Sv/hr$ at 100 cm. 24 hours after the patient was treated with 180 mCi high-dose iodine, the dose rate was attenuated to $1,251{\mu}Sv/hr$ at the navel, $140{\mu}Sv/hr$ at 50 cm, and to $56{\mu}Sv/hr$ at 100 cm. In light of the current criterion for discharge recommended by the US Nuclear Regulatory Commission being $70.4{\mu}Sv/hr$, the present study indicates earlier discharge is feasible by applying a new scheme. This suggests that the proposed scheme in this study will help to solve the problem of shortage of treatment beds with the increasing trend of patients with thyroid cancer taken into consideration.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.15 no.3
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• pp.265-279
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• 2017

The Gyeongju underground silo type disposal facility, approved for use in December 2014, is in operation for the disposal of low and very low-level radioactive wastes, excluding intermediate-level waste. That is why the existing low-level radioactive waste level has been subdivided and the concentration limit value for intermediate-level waste has been changed in accordance with Nuclear Safety Commission Notice 2014-003. For the safe disposal of intermediate-level wastes, new optimization methodology for calculating the concentration limit of intermediate radioactive level wastes at an underground silo type disposal facility was developed. According to the developed optimization methodology, concentration limits of intermediate-level wastes were derived and the inventory of radioactive nuclides was evaluated. The operation and post closure scenarios were evaluated for the derived radioactive nuclide inventory and the results of all scenarios were confirmed to meet the regulatory limit. However, in case of $^{14}C$, it was confirmed that additional radioactivity limitation through a well scenario was needed in addition to the limit of disposal concentration. It was confirmed that the derived intermediate concentration limit of radioactive waste can be used as the intermediate-level waste concentration limit for the underground disposal facility. For the safe disposal of intermediate-level wastes, KORAD plans to acquire additional data from the radioactive waste generator and manage the cumulative radioactivity of $^{14}C$.