Shielding Evaluations of Fuel Failure Scenarios Using MAVRIC

Kyoon-Ho CHA,Minchul KIM,Taehyeon KIM 한국방사성폐기물학회 2018 한국방사성폐기물학회 학술논문요약집 Vol.2018 No.10

Monte Carlo 방법을 이용한 바나듐 자발 중성자계측기 초기 민감도 계산

차균호 ( Kyoon Ho Cha ),박영우 ( Young Woo Park ) 한국센서학회 2016 센서학회지 Vol.25 No.3

Self-powered neutron detector (SPND) is being widely used to monitor the reactor core of the nuclear power plants. The SPND contains a neutron-sensitive metallic emitter surrounded by a ceramic insulator. Currently, the vanadium (V) SPND has been being developed to be used in OPR1000 nuclear power plants. Some Monte Carlo simulations were accomplished to calculate the initial sensitivity of vanadium emitter material and alumina insulator with a cylindrical geometry. An MCNP code was used to simulate some factors (neutron self-shielding factor and beta escape probability from the emitter) and space charge effect of an insulator necessary to calculate the sensitivity of vanadium detector. The simulation results were compared with some theoretical and experimental values. The method presented here can be used to analyze the optimum design of the vanadium SPND and contribute to the development of TMI (Topmount In-core Instrumentation) which might be used in the SMART and SMR.

한 정신병원에서의 강박 처치에 대한 입원 환자 및 병원 직원의 지각의 차이

채정호,차성조,함웅,이규항,이정균 大韓神經精神醫學會 1996 신경정신의학 Vol.35 No.5

한 정신병원에서 강박처치의 적응증, 합병증, 대체법, 감정적 영향, 적당한 처치 시간, 처치의 효능과 필요성등을 병원에 입원 중인 환자들과 직원들에게 설문조사를 하여 양 집단간에 차이가 있는 지를 알아봄으로써 환자들과 직원들간에 있는 강박처치에 대한 지각 차이를 조사하고 나아가 강박처치 시행의 규준을 확립하기 위한 기본 자를 제시하기 위하여 본 연구를 시행하였다. 강박처치의 적응증에 대해서 입원환자들은 대부분의 항목에 대해 부정적으로 보았고 단지 타환자에 대한 신체적 공격에 대해서만 다소 긍정적인 반응을 보인 반면 직원들의 경우 자해, 타환자에 대한 신체적 공격, 치료진에 대한 공격 등에 높은 응답율을 보였다. 강박처치의 부작용에 대한 지각은 입원환자의 경우 정신상태의 악화, 자해의 증가 등에 대해 보다 민감하게 반응 하였고, 실제로 경험한 부작용에 있어서는 직원들의 경우 피부박탈을 더 강조한 반면 환자군에서는 호흡곤란, 정신 상태의 악화 등을 강조하였다. 강제 처치에 대한 대체치료 방법으로는 환자군에서 면담을 중요시한 반면 직원군에서는 격리실의 이용을 강조하였다. 신체억제와 고용량의 정온화를 비교한 것은 환자군에서 신체억제가 더 효과적이라고 하였다. 신체억제 동안 느끼는 감정에 대한 지각에서 환자군은 슬픔을 가장 많이 보고하였고, 직원군은 적개심을 가장 많이 느낄 것으로 추정하였다. 신체억제의 시간에 대해서는 환자군이 긴 것으로 지각하고 있으며, 이상적인 신체억제의 시간은 환자군이 짧은 것이 좋다고 생각하고 있었다. 본 연구 결과 정신과 입원환자들과 병원직원들은 강박처치에 대하여 유의한 지각의 차이가 있다는 것을 알았으며 정신병원내에서 강제처치를 실시할 때에는 명확한 강박처치 시행에 대한 규준에 따라야 할 것임을 확인할 수 있었다. Objectives : The purpose of this study was to examine different perceptions of physical restraint and their nature between psychiatric inpatients and hospital staffs in a mental hospital and to provide baseline data for establishing the practicing standard of this therapeutic maneuver. Methods : Two hundred and two psychiatric inpatients who experienced physical restraint and 103 hospital staffs who frequently used this maneurer were surveyed with a questionnaire regarding indications, complications, alternative methods, emotional influences, duration of treatment and subjective effects of restraint. Results : Regarding indications of physical restraint, the inpatient group had negative viewpoint on the most items except "physical assault to other patients". Regarding the perception about possible complications of this treatment, the inpatient group had more concerns about "deterioration of mental status" and "increasing risk of self-injury". For experienced complications, staffs stressed "skin abrasion " while inpatients believed of "respiratory difficulties" and "deterioration of mental status" more frequently. As alternative methods of physical restraint, "increasing frequency of interview" was suggested by the inpatient group and "using seclusion room" was favored by the staff group. The inpatient group had an impression that physical restraint was more effective than high-dose neuroleptic tranquilization. For suspected emotion during this procedure, the inpatient group reported "sorrow" most frequently while the staff group presumed that "hostility" might be most frequent. Inpatients estimated that the average duration of physical restraint was longer than staffs did. Ideal duration of physical restraint was shorter in the inpatient group. Conclusion : These results suggest that there are definite differences in the perception of physical restraint between psychiatric inpatients and hospital staffs. Formal practing guideline for restraint should be set up with careful attention for these differences to maximize the therapeutic effect of this maneuver.

해조류 부산물을 이용한 액체비료 제조에 관한 연구

안호근 ( Ho-geun Ahn ),조주식 ( Ju-sik Cho ),강종구 ( Jong-gu Kang ),김홍림 ( Hong-limkim ),차규석 ( Gyu-suk Cha ),손보균 ( Bo-kyoon Sohn ) 한국환경기술학회 2005 한국환경기술학회지 Vol.6 No.3

우리나라 남해안 연안의 양식현장에서 폐기되는 해조류 양식 부산물을 사용하여 액체비료를 제조하고 그 특성을 조사하였다. 실험재료는 다시마, 미역과 톳을 파쇄하거나 건조시켜 사용하고 첨가제로는 알칼리 용액을 사용하였다. 종류별 해조류는 많은 미네랄 성분을 함유하고 있고, 중금속은 검출되지 않았다. 해조류의 용해에는 KOH보다 NaOH 용액이 효율적이었다. NaOH 용액으로 제조한 해조류 용액은 인산용액으로 중화하고 적정한 배율로 희석하였다. 폐 미역의 최적 용해조건은 NaOH 용액에 대한 해조류의 비를 1:1로 하고, 용해온도는 80℃, 용해시간은 12시간정도이었다. 제조한 액체비료에서 중금속은 전혀 발견되지 않았고, 해조류내에 존재하는 오옥신과 사이토키닌과 같은 식물생장 호르몬은 용해과정을 거치더라도 분해되지 않았다. 결과적으로 해조류의 부산물을 NaOH 용액으로 용해하면 액체비료로 사용할 수 있는 특성을 가짐을 확인하였다. In order to reutilize the seaweeds which were spent on the culture field in Korean South coast and in industrial processes, fluid fertilizer was prepared by dissolving the seaweed into alkali solutions. Effective solvent and method for seaweed dissolution and properties of the solutions were studied. Undaria sp., Laminaria sp., and Hizikia fusiforma were used as raw sources of seaweed. The seaweed solutions were prepared by heating an alkali solution containing the seaweed. All seaweeds contained much mineral constituents, did not hazardous metals. Dissolution efficiency was evaluated by pH and viscosity of the solutions. Various seaweeds were well dissolved in alkali solution, especially NaOH solution. Seaweed solution prepared by NaOH solution could be neutralized using a H3PO4 solution to be used to spray for plant growth. In dissolution of spent Undaria sp, optimum ratio of seaweed to NaOH solution, temperature, required time were 1, 80℃, and 12 hours, respectively. Also, the hormones in seaweeds for plant growth such as Auxin and Cytokinin were not destroyed in dissolution process. As a result, it was confirmed that the seaweed concentrate from dissolution with NaOH solution could be utilized as a fluid fertilizer.

말라리아 환자에서의 자발적 비장 파열

박민호(Min Ho Park),차정곤(Jeong Gon Cha),구원회(Won Hoe Koo),노정호(Jeong Ho Rho),조철균(Chol Kyoon Cho),김현종(Hyun Jong Kim) 대한외과학회 2000 Annals of Surgical Treatment and Research(ASRT) Vol.59 No.4

Establishment and Application of Nuclear Criticality Safety Validation Methodology

Seo Jeong Lee,Kyoon Ho Cha 한국방사성폐기물학회 2018 방사성폐기물학회지 Vol.16 No.3

미임계 시설은 정상 또는 사고상태에서 핵임계안전성이 확보되어야 한다. 이를 위해선 계산된 임계도가 바이어스와 불확실도로 결정된 미임계상한치(USL)를 초과하지 않는다는 것을 검증하는 절차가 반드시 필요하다. 하지만 핵임계안전성 검증 방법론은 여러 가지가 존재하며, 방법론이 달라지면 USL도 달라지므로 가장 적절한 한가지의 방법론으로 평가하는 것이 중요하다. 본 연구에서는 핵임계안전성 검증 방법론이 기술된 두 개의 문서를 비교 분석하여 한 가지 방법론으로 정립하였고, SCALE6.1 코드를 이용한 용기 설계에서의 미임계상한치 결정에 적용하였다. A subcritical facility must ensure nuclear criticality safety under all circumstances. For this purpose, it is essential to have a procedure to validate that calculated values do not exceed upper subcritical limit (USL), determined by quantifying the bias and uncertainty. However, there are several validation methodologies of nuclear criticality safety and these can yield different USL. Therefore, it is necessary to analyze the validity of the methodologies to establish one methodology that can provide the most appropriate USL. In this study, two documents, a guide for validation of nuclear criticality safety calculational methodology (NUREG/CR-6698) and a criticality benchmark guide for light water reactor fuel in transport and storage package (NUREG/CR-6361), are compared and analyzed. In particular, the methodology in NUREG/CR-6361 is applied to the USLSTATS code. However, the analysis results show that the methodology in NUREG/ CR-6698 is more appropriate, for several reasons. This is applied to decision of USL to design casks using SCALE code version 6.1.

New calculational model for self-powered neutron detector based on Monte Carlo simulation

Lee, Hyunsuk,Choi, Sooyoung,Cha, Kyoon-Ho,Lee, Kwangho,Lee, Deokjung Atomic Energy Society of Japan 2015 Journal of nuclear science and technology Vol.52 No.5

수혈을 거부하는 대량 혈복증 환자의 무수혈적 수술 및 치료

최일(Il Choi),차정곤(Jeong Gon Cha),노정호(Jung Ho Roh),조철균(Chol Kyoon Cho),김현종(Hyun Jong Kim) 대한외과학회 2000 Annals of Surgical Treatment and Research(ASRT) Vol.58 No.2

The Spent Fuel Information System Development Based on Semantic Technology

Hong-Jin Kim,Young-Chul Cho,Kyoon-Ho Cha 한국방사성폐기물학회 2023 한국방사성폐기물학회 학술논문요약집 Vol.21 No.2

In the establishment of procedures for managing spent fuel, the development of an information system for data management is an indispensable prerequisite. Given the prolonged period of spent nuclear fuel management, marked by numerous personnel changes and the anticipation of vast data retention, addressing this matter appropriately is imperative, particularly in the specialized field of spent nuclear fuel operations. Recognizing the need for a method to mitigate these challenges, we endeavored to apply semantic technology to the information system. To achieve this, we constructed the ontology of spent nuclear fuel and conducted research to transform it into a relational database. As a result, the information system, developed by the application of semantic technology, has attained the capability to comprehend and perceive relationships among information itself. Through this research, the system not only addresses previously identified concerns but also enhances its versatility, enabling it to perform functions previously unattainable within existing information systems.

핵임계 안전성 검증 방법론 정립 및 적용

이서정,차균호,Lee, Seo Jeong,Cha, Kyoon Ho 한국방사성폐기물학회 2018 방사성폐기물학회지 Vol.16 No.3

A subcritical facility must ensure nuclear criticality safety under all circumstances. For this purpose, it is essential to have a procedure to validate that calculated values do not exceed upper subcritical limit (USL), determined by quantifying the bias and uncertainty. However, there are several validation methodologies of nuclear criticality safety and these can yield different USL. Therefore, it is necessary to analyze the validity of the methodologies to establish one methodology that can provide the most appropriate USL. In this study, two documents, a guide for validation of nuclear criticality safety calculational methodology (NUREG/CR-6698) and a criticality benchmark guide for light water reactor fuel in transport and storage package (NUREG/CR-6361), are compared and analyzed. In particular, the methodology in NUREG/CR-6361 is applied to the USLSTATS code. However, the analysis results show that the methodology in NUREG/CR-6698 is more appropriate, for several reasons. This is applied to decision of USL to design casks using SCALE code version 6.1.