• Proceedings of the Korean Nuclear Society Conference
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• 1995.05b
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• pp.1087-1092
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• 1995

MOX 연료는 PWR, BWR, FBR 및 ATR 등과 같은 다양한 노형에서 이용이 가능하다. 이와 같은 MOX 연료는 이미 일부 국가에서 이들 노형에 이용하고 있으며, FBR의 상용화 시기가 다소 지연될 것으로 예상되어 이 분야에 대찬 연구는 더욱 활발히 진행될 전망이다. 여기에서는 이와 같은 현실을 감안하여 MOX 연료를 이용하는 MOX 연료주기와 우라늄 연료만을 이용하는 우라늄 연료주기에 대한 핵연료주기비를 비교·분석하였고, 그 결과 MOX 연료주기와 우라늄 연료주기의 경제성은 거의 대둥한 것으로 평가되었다. 또한 우라늄 가격, 사용후핵연료 처분시기, 처분 비용/재처리비용 등의 주요 변수에 대한 민감도분석을 수행한 결과, MOX 연료주기가 우라늄연료주기에 대해 상당한 경쟁력을 가지고 있는 것으로 분석되었다.

• Journal of Energy Engineering
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• v.25 no.2
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• pp.52-64
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• 2016

The production of nuclear energy from thorium which is non-fissile material was a main issue until the middle of 1970's, because of the thorium's abundance as energy resources, its capability of breeding fissile material U233, and the reduction of long-lived actinides. However, to use thorium as nuclear fuel, some obstacles such as the necessities of external neutron source and long-term neutron irradiation for effective breeding, and the production of high radioactive isotopes in the course of thorium breeding cycle should be overcome. The difficulties to resolve these cons of thorium cycle became the reason of interruption of the related researches in the middle of 1970's. But in the 21st century, the change of societal perspective regarding nuclear energy and the appearance of accelerator-driven nuclear reactor shift those cons into pros and rehabilitate the study of thorium. The high activity of thorium cycle turned out to be a good option as higher resistance and easier detectibility of nuclear proliferation and the employment of subcritical accelerator-driven reactor as external neutron sources is considered to enhance the nuclear safety. In this study we compare the thorium cycle with the currently-used uranium cycle and analyze the technical status and perspective of thorium researches which use accelerator-driven reactors.

• Proceedings of the Korean Nuclear Society Conference
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• 1998.05a
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• pp.64-69
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• 1998

KALMER 우라늄 금속핵연료노심의 평형주기에 대하여 주기길이, 농측도, 중식비의 관점에서 설계인자 변경에 따른 변화를 분석하였다. 유효노심높이, 반경방향 블랑캣의 batch수, 개스팽창모듈(GEM)의 적용성, 노용기내핵 연료저장(IVS)의 사용. 핵연료핀의 직경 증가 둥에 대한 설계 변경이 고려되었다. 본 연구결과를 통하여, 평탄화된 출력분포 및 핵연료의 이용도 향상을 기하면서 설계변경이 타 분야에 미치는 영향을 최소화하고 본래 KALMER의 안전성을 유지하고자 핵연료핀의 직경을 증가시킨 fat pellet 설계방안을 채택하였다

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.5 no.4
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• pp.283-295
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• 2007

The technical feasibility of a pyroprocessing of PWR spent fuels to recover nuclear fuel materials, uranium and transuranic elements group(TRU), was examined in this study. Also its applicability as a new fuel cycle technology in terms of non-proliferation was investigated. First, various unit processes were combined to a pyroprocess. Then the flow aspects of such materials of issue as uranium, transuraniums, rare earth, noble metals and heat generating elements were examined on the flowsheet, which was obtained by the assumptions on the basis of various experimental results in this work or separation data collected from literatures. Consequently, the calculated results of the material balance for the whole process showed that uranium and TRU could be recovered as products by 98.0 % and 97.0 %, respectively, from a PWR spent fuel while removing the other elemental groups into radioactive wastes. On the one hand, the TRU product was found to emit a considerable amount of ${\gamma}$-ray as well as neutrons favorably contributing to the strategy of proliferation resistance.

• Nuclear industry
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• v.8 no.1 s.59
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• pp.68-76
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• 1988

지금까지 전세계의 원자로 기수와 위치에 대해서는 많은 관심을 갖고 있는 반면 핵연료주기시설에 대해서는 무심하였다. 최근 Nuclear Engineering International지가 예로케이크$(U_3O_8)$형태 이후의 우라늄을 취급하는 시설을 조사하여 '87년 12월호에 게재하였다. 다음은 각국의 핵연료주기 관련 플랜트의 위치, 소유주 및 그 용량 등을 정리한 것이다.

• Journal of the Korean Society of Radiology
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• v.15 no.1
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• pp.37-43
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• 2021

Republic of Korea has many nuclear facilities in the country, and Democratic People's Republic of Korea(North Korea) locates in the surrounding country. Therefore, it is necessary to construct the target facility's nuclear forensic data in a preemptive response to the changing international situation. For this reason, this study suggests "signature" materials used to understand the origins and sources of nuclear and other radioactive materials, taking into account domestic nuclear facilities and the nuclear fuel cycle. In domestic, pressurized light water reactors and pressurized heavy water reactors are in operation, and enriched and natural uranium are used as fuels. In the front-end fuel cycle, the signature materials can be nature uranium and UF6 in the uranium enrichment process. The domestic back-end fuel cycle adopts a non-circulating cycle excluding the reprocessing process, and the primary signature material is spent nuclear fuel. According to IAEA recommendation, the importance of these materials as the signature and characteristic contents are suggested in this study. To prove the integrity of nuclear material and build a national nuclear forensics library, it is necessary to grasp the signature material and acquire the characteristic data considering the domestic nuclear facilities and the nuclear fuel cycle.

• Nuclear Engineering and Technology
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• v.9 no.3
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• pp.139-149
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• 1977

An attempt is made to establish an optimum fuel cycle strategy for the Go-ri nuclear power plant units 1 and 2. The total capital required for the fuel cycle operation is selected as a figure of merit for economic comparison of several alternative fuel cycle schemes available for the plant, and evaluated using a probabilistic method coupled with a sampling procedure of the fluctuating fuel cost data. The results are presented in the form of probability histograms. On the basis of the most likely values of the capital requirement obtained from the histograms, a conclusion is drawn that reprocessing cycle with either uranium only or both uranium and plutonium recycled is the most economic choice for the Go-ri plant.

• Proceedings of the Korean Nuclear Society Conference
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• 1996.05a
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• pp.213-218
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• 1996

가압 경수로의 노심설계에 있어서 제한된 우라늄 자원의 효율적인 이용을 위한 다양한 방안으로 장주기 운전, 고 방출연소도 및 저누출 장전모형 등을 강구하고 있는 추세이다. 이러한 노심들은 원자로 운전주기 전반에 걸친 공간적 출력 분포 제어와 잉여반응도 제어를 위해 가연성 흡수봉을 사용하고 있으며 이와 관련 하여 가연성 흡수봉에 대한 전략등이 다 각도로 검토되고 있으며 다양한 노심에 대한 최적의 가연성 흡수봉 혹은 그 전략에 대해 많은 연구가 진행되고 있다. 본 연구에서는 웨스팅하우스형 3-Loop 발전소에 대해, 장주기 (18 개월-480 EFPD), 저누출 장전 모형 전략을 채용하여, Er$_2$O$_3$, Gd$_2$O$_3$, ZrB$_2$의 일체형 가연성 흡수봉에 대한 노심특성 및 경제성을 평형노심개념을 적용, KNFC가 노심설계에 사용하고 있는 APA(ALPHA/PHOENIX-P/ANC) 8.0.0 코드 체계를 이용하여 평가하였다. 노심특성에 대해서는 감속재 온도계수, 첨두출력인자, 잔존흡수봉효과 및 노심 연소거동에 대한 평가가 수행되었고, 동일한 주기길이(480 EFPD) 에 대한 우라늄 적재량에 대해 원광비, 변환비, 농축비, 가공비 그리고 이자율 등을 고려하여 핵주기 경제성 평가 코드인 POCO 코드를 이용하여 경제성을 평가하였다.

• Proceedings of the Korean Nuclear Society Conference
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• 1997.05a
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• pp.96-101
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• 1997

양자가속기를 외부 중성자 공급원으로 하여 미임계 운전을 가능하게 하고 토륨을 핵연료로 사용하므로 장주기 핵종과 핵무기 재료물질의 발생량을 현저히 줄일 수 있는 새로운 노형인 energy amplifier에 대한 연구가 CERN을 중심으로 활발히 진행되고 있다. 본 연구에서는 토륨주기에 대하여 고정 중성자속 조사에 의한 핵분열 및 방사붕괴에 관한 모델을 정립하여 다수의 연립선형 미분방정식으로 구성하여 Runge Kutta 5-6차 자동시간 간격 수치해법을 이용하여 계산하였다. 결과는 1014의 고정 중성자속에 대하여 충분한 U233의 생산이 평형상태에 도달하고 장주기 핵종도 우라늄 주기에 비하여 현저히 줄어듬을 보이므로 가속기를 이용한 토륨 핵연료 주기의 타당성을 확인하였다.

• Journal of Radiation Protection and Research
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• v.38 no.2
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• pp.68-77
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• 2013

Derived Investigation levels(DILs) were calculated to protect the workers from the effects of both radiological hazard and chemical toxicity by uranium intake. Investigation Levels(ILs) of committed effective dose of 2 mSv $y^{-1}-6$ mSv $y^{-1}$ and uranium concentration of 0.3 ${\mu}g$ $g^{-1}$ in kidney, based on Korean Nuclaer Safety Act, Korean Occupational Safety and Health Act and current scientific studies of uranium intake were assumed. DILs of radiological hazard and chemical toxicity were then calculated based on the concentration of uranium in air of workplace, the lung monitoring and urine analysis, respectively. As a result, in case of the nuclear fuel fabrication plant where 3.5% enriched uranium is handled, derived investigation level(DIL) for the control of the concentration of uranium in the air of workplace assumed with 15-min acute inhalation was 0.6 mg $m^{-3}$ for all types of uranium. DILs for the control of the average concentration of uranium in air of workplace, assuming an 8-hour workday, were 15.21 ${\mu}g$ $m^{-3}$ of Type F uranium, 0.41-1.23 Bq $m^{-3}$ and 0.13-0.39 Bq $m^{-3}$ for Type M and Type S uranium, respectively. DILs for the lung monitoring assumed with a period of 6-month interval were 0.37-1.11 Bq and 0.39-1.17 Bq in acute and chronic inhalation for Type M, respectively and 0.30- 0.91 Bq and 0.19-0.57 Bq in acute and chronic inhalation for Type S, respectively. Since a detection limit of typical germanium detector for the measurement of 235U activity is 4 Bq, DILs calculated for the lung monitoring were not appropriate. DILs for urine analysis, for which an interval was assumed to be 1 month, were 14.57 ${\mu}g$ $L^{-1}$ based on chemical toxicity after acute inhalation. In addition, acute and chronic inhalation of Type M were calculated 2.85-8.58 ${\mu}g$ $L^{-1}$ and 1.09-3.27 ${\mu}g$ $L^{-1}$ based on the radiological hazard, respectively.