• Nuclear Engineering and Technology
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• v.25 no.2
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• pp.237-247
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• 1993

Activity ratio of two radioactive primary fission products which had sufficiently different half-lives was expressed as functions of cooling time and irradiation histories in which average burnup, irradiation time, cycle interval time and the dominant fissile material of the spent fuel were included. The gamma-ray spectra of 36 samples from 6 spent PWR fuel assemblies irradiated in Kori unit-1 reactor were obtained by a spectrometric system equipped with a high purity germanium gamma-ray detector. Activity ratio $^{l44}$Ce $^{l37}$Cs, analyzed from each spectrum, was used for the calculation of cooling time. The results show that the radioactive fission products $^{l44}$Ce and $^{l37}$Cs are considered as useful monitors for cooling time determination because the estimated cooling time by detection of activity ratio $^{l44}$Ce $^{l37}$Cs agreed well with the operator declared cooling time within relative difference of $\pm$5 % despite the low counting rate of the gamma-ray of $^{l44}$Ce (about 10$^{-3}$ count per second). For the samples with several different irradiation histories, the determined cooling time by modeled irradiation history showed good agreement with that by known irradiation history within time difference of $\pm$0.5 year. From this result, it would be expected to be possible to estimate reliably the cooling time of spent nuclear fuel without the exact information about irradiation history. The feasibility study on identification of and/or sorting out spent nuclear fuel by applying the technique for cooling time determination was also performed and the result shows that the detection of activity ratio $^{l44}$Ce $^{l37}$Cs by gamma-ray spectrometry would be usefully applicable to certify spent nuclear fuel for the purpose of safeguards and management in a facility in which the samples dismantled or cut from spent fuel assemblies are treated, such as the post irradiation examination facility.mination facility.

• Proceedings of the Korean Society of Postharvest Science and Technology of Agricultural Products Conference
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• 2003.10a
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• pp.205.2-205
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• 2003

가정에서는 쌀을 소비할 때 외기 조건 특히, 하절기와 같이 외기 온도가 높을 경우 함수율 감소, 지방산가 증가 및 해충발생 등 품질 손상이 급격히 발생한다. 따라서, 가정에서 쌀을 소비할 때 쌀의 품온을 가능한 낮춰 안전하게 저장하는 방법이 필요하다. 본 연구는 가정용 냉각쌀통을 이용하여 저온에서 쌀을 저장하면서 저장기간 중 품질변화를 측정하여 저온저장특성을 구명하는데 목적이 있다. 가정용 냉각쌀통은 매직 쌀장고(MRH-2501, Tongyang)를 이용하였으며, 대조구로 상온($25^{\circ}C$)에서 쌀을 14주간 저장하면서 1주일 간격으로 시료를 채취하여 함수율, 지방산가, 색도 및 표면변화를 측정하였다. 저장기간이 경과함에 따라 쌀의 함수율은 냉각쌀통의 경우 1.5%(w.b.), 상온저장의 경우 2.1%(w.b.)가 감소하였다. 지방산가는 냉각쌀통에서 저장 14주 후15.1(mg KOH/100g)로 나타났고, 상온저장에서는 8주 후 24.2, 14주 후에는 40.9(mg KOH/100g)로 급격히 증가하였다. 쌀의 색도는 저장기간이 경과함에 따라 증가하는 경향으로 나타났으며, 상온저장이 냉각쌀통에 비해 현저히 높게 증가하였으며, 저장 8주 후부터는 유의적인 차이를 나타내었다. 쌀의 표면에 세포벽은 냉각쌀통에 비해 상온저장에서 저장기간이 경과함에 따라 뚜렷하게 나타났다.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.6 no.1
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• pp.65-72
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• 2008

The purpose of the HLW deep geological disposal is to isolate and to delay the radioactive material release to human beings and the environment for a long time so that the toxicity does not affect to the environment. The main requirements for the HLW repository design is to keep the buffer temperature below $100\;^{\circ}C$ in order to maintain its integrity. So the cooling time of spent fuels discharged from the nuclear power plant is the key consideration factors for efficiency and economic feasibility of the repository. The disposal tunnel/disposal hole spacing, the disposal area and thermal capacity required for the deep geological repository layout which satisfies the temperature requirement of the disposal system is analyzed to set the optimized spent fuels cooling time. To do this, based on the reference disposal concept, thermal stability analyses of the disposal system have been performed and the derived results have been compared by setting the spent fuels cooling time and the disposal tunnel/disposal hole spacing in various ways. From these results, desirable spent fuels cooling time in view of disposal area is derived. The results shows that the time reaching the maximum temperature within the design limit of the temperature in the disposal site is likely shortened as the cooling time of spent fuels becomes short. Also it seems that the temperature-rising and-dropping patterns in the disposal site are of smoothly varying form as the cooling time of spent fuels becomes long. In addition, it is revealed that a desirable cooling time of spent fuels is approximately 40-50 years when spent fuels are supposedly disposed in the deep geological disposal site with its structural scale under consideration in this study.

• Proceedings of the Korean Nuclear Society Conference
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• 1998.05a
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• pp.707-712
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• 1998

이종 코드에 의한 CE형 발전소의 대형 냉각재 상실 사고 해석이 수행되었다. 이 연구는 상대적으로 최근에 개발된 웨스팅하우스 대형 냉각재 상실 사고 해석 코드를 사용하여 영광 3&4호기의 대형 냉각재 상실 사고를 계산해 봄으로써 CE 대형 냉각재 상실 사고 해석 코드의 개선 방향을 고찰하는 것을 목적으로 하였다. 계산은 가장 제한적인 대형 냉각재 상실 사고의 Blowdown 및 Refill 기간 동안 수행하였다. 이 기간 동안의 RCS내 열수력적 거동 및 연료봉 온도 변화는 CE 대형 냉각재 상실 사고 해석 코드를 사용하여 계산한 경우와 크게 다르지 않음을 확인하였다. 따라서 향후 CE 대형 냉각재 상실 사고 해석 코드의 성능 개설은 Reflood 해석용 코드의 개선 및 개발을 중심으로 이루어져야 한다는 결론을 얻었다.

• Proceedings of the Korean Nuclear Society Conference
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• 1996.11a
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• pp.103-109
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• 1996

고리 원자력 1호기 14주기(‘95년도) 운전기간 중 증기발생기 세관 열전달 용량 저하로 전출력 운전 기간동안 정격출력보다 15% 감발 운전한 경험이 있었는데, 이 기간중 냉각재내 방사성 부식생성물(CRUD) 농도가 약 80% 감소됨을 발견하였다. 이때 출력감소 비율보다 많은 CRUD 감소현상 규명을 위해 냉각재 수질관리인자와 EPRI 피복재 부식모델인 PFCC코드를 사용한 피 복재 산화물 두께변화 등을 비교한 결과, 운전중 용출되는 방사성 부식생성물은 핵연료 표면의 피복재 산화물에 흡착된 Co핵종이 피복재 산화물 이탈시 함께 거동하는 것으로 확인되었으며, 피복재 산화물 이탈은 산화막 두께 및 열유속에 주로 의존함이 밝혀졌다. 따라서 냉각재내에서 방사성 부식 생성물의 생성률 저감을 위해서는 정상운전시 핵연료 표면의 산화막 증가를 억제할 수 있는 수질 조건을 도출하고 그에따른 운전을 통해 원전 작업자의 방사선 피폭량 저감 및 방사성폐기물의 발생을 줄일 수 있을 것으로 여겨진다.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.17 no.3
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• pp.339-346
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• 2019

Based on the $8^{th}$ Basic Plan for Electric Power Demand and Supply, an estimation has been made for inventories and characteristics of spent fuel (SF) to be generated from existing and planned nuclear power plants. The characteristics under consideration in this study are dimensions, fuel array, $^{235}U$ enrichment, discharge burnup, and cooling time for each fuel assembly. These are essentially needed for designing a disposal facility for SFs. It appears that the anticipated quantity by the end of 2082 is about 62,500 assemblies for PWR SFs. The inventories of Westinghouse-type and Korean-type SFs were revealed to be 60% and 40%, respectively as of the end of 2018. The proportion of SFs with initial $^{235}U$ enrichment below 4.5 weight percent (wt%) was shown to be approximately 90% in total as of the end of 2018. As of 2077, more than 97% of SFs generated from Westinghouse-type nuclear reactors were shown to have cooling time of over 50 years. As of 2125, more than 98% of SFs generated from Korean-type nuclear reactors were shown to have cooling time of over 45 years. Based on these results, for the efficient design of a disposal system, it is reasonable to adopt two types of reference spent fuel. SF of KSFA with $^{235}U$ enrichment of 4.5 wt%, discharge burnup of 55 GWd/tU, and cooling time of 50 years was determined as reference fuel for Westinghouse-type SFs; SF of PLUS7 with $^{235}U$ enrichment of 4.5 wt%, discharge burnup of 55 GWd/tU, and cooling time of 45 years was determined as reference fuel for Korean-type SFs.

• Korean Journal of Food Science and Technology
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• v.27 no.2
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• pp.241-245
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• 1995

Focusing on quality problems of delayed chilling porcine muscle, the effects of delayed chilling and aging on the contents of ATP-related compounds and taste of pork were investigated. Twelve Landrace pigs were employed and bisected: left sides were delay-chilled(DC) at room temperature($20^{\circ}C$) for 3 hrs, whereas right sides were conventionally chilled(CC). ATP-related compounds tested were adenosine triphosphate(ATP) and its derivatives in pork muscle, inosine monophosphate(IMP), guanosine monophosphate(GMP) and L-glutamate in cooked broth. DC sides showed more rapid pH decline and degradation of nucleotides than did CC sides. The levels of ATP and adenosine monophosphate(AMP) were not changed significantly. However, adenosine diphosphate(ADP) and IMP showed the highest levels at the 1st and 5th day, respectively. Hypoxanthine(Hx) was gradually increased(p<0.05) during aging. During aging, the IMP contents cooked broth tended to decrease, while the GMP and L-glutamate contents increase. As a result of these, the taste score got better and finally the results of sensory evaluation became increased(p<0.05). However, compared to CC sides, DC sides did not seem to lower taste of pork.

• Proceedings of the Korean Nuclear Society Conference
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• 1998.05b
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• pp.458-463
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• 1998

고준위방사성페기물의 기준 처분시스템 (Reference Geological Disposal System)의 개념설정을 위하여 현재 국내 원전에서 발생되고 있거나 향후 2010까지 건설될 원전으로부터 발생될 모든 사용 후 핵연료연료의 특성(크기, 무게, 초기농축도, 연소도, 냉각기간 등)을 대표할 수 있는 기준 사용 후 핵연료를 선정하였다.

• Proceedings of the Korean Nuclear Society Conference
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• 1996.05c
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• pp.470-475
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• 1996

사용후핵연료 장기 건식저장시 여러가지 저장조건에서 사용후핵연료 피복관 및 사용후핵연료 ($UO_2$)에 대한 장기 건전성을 종합적으로 평가할 수 있는 SIECO 코드를 개발하였다. 건식저장 시스템은 사용후핵연료를 헬륨 및 공기분위기하에서 TN-24P 건식 저장용기에 장기 저장할 경우로 하였으며 피복관의 최대 표면온도는 COBRA-SFS코드를 사용하여 계산하였고, 열유동 해석결과를 바탕으로 SIECO코드를 이용하여 핵연료 연소도 및 냉각기간, 냉각매체에 따른 최대 건식저장 허용온도를 피복관의 열화 및 $UO_2$ 산화의 관점에서 계산하였다.

• Proceedings of the Korean Nuclear Society Conference
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• 1997.10a
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• pp.357-362
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• 1997

PWR 원전 계획 예방정비 기간 중에는 Crud 제거를 위한 정지화학 제어가 수행되고 있으나, 불시정지시 화학제어에 대한 접근은 거의 전무하다. 이에, 정지시 냉각재화학 변화에 따른 Nickel Ferrite의 안정성에 대해 검토하고, 불시정지시 냉각재 화학제어의 방향을 도출하였다. 계획정지 화학제어가 가능한 불시정지시에는 Nickel Ferrite 용출 증대를 위한 조기 붕산화와 고농도 용존수소 (Fig. 1 참조) 유지 및 산성-산화 단계의 도입이, 적용이 불가능한 경우에는 Nickel Ferrite 용출 억제를 위한 붕산화 연기 및 용존수소의 저농도 유지가 타당할 것이다.