방사성패기물 처분시설에서의 완충공간 설정에 대한 고찰

윤정현,박주완,주민수,김창락,박진백,Yoon, Jeong-Hyoun,Park, Joo-Wan,Ju, Min-Su,Kim, Chang-Lak,Park, Jin-Baek 한국방사성폐기물학회 2008 방사성폐기물학회지 Vol.6 No.1

A new proposed repository has a final capacity of 800,000 drums radioactive waste. Most of foreign repositories have a general practice of segregating control zones which mainly contributes to classification of degree of control, whether it is called buffer zone or not. Domestic regulatory requirements of establishment of buffer zone in a repository are not much different from those of nuclear power plants for operation period, in which satisfactory design objective or performance objective is the most important factor in determination of the buffer zone. The meaning of buffer zone after closure is a minimum requested area which can prevent inadvertant intruders from leading to non-allowable exposure during institutional control period. Safety assessment with drinking well scenario giving rise to the highest probability of exposure among the intruder's actions can verify fulfillment of the buffer zone which is determined by operational safety of the repository. At present. for the repository to be constructed in a few years, the same procedure and concept as described in this paper are applied that can satisfy regulatory requirements and radiological safety as well. However, the capacity of the repository will be stepwise extended upto 800,000 drums, consequently its layout will be varied too. Timely considerations will be necessary for current boundary of the buffer zone which has been established on the basis of 100,000 drums disposal.

Determination of Design Basis for a Storage System for Spent Fuel in Korea

윤정현,이은용,우상인,김태만,Yoon, Jeong-Hyoun,Lee, Eun-Yong,Woo, Sang-In,Kim, Tae-Man Korean Radioactive Waste Society 2011 방사성폐기물학회지 Vol.9 No.2

원자력발전소에서 나온 사용후핵연료 건식저장시스템의 안전한 운영과 유지는 기본적으로 적절하게 선택된 설계기준에 좌우된다. 저장시스템의 가장 중요한 설계목표는 저장된 사용후핵연료로부터 작업자의 안전과 대중에게 과도한 위험이 없이 보관, 취급, 수납 및 감시할 수 있는 신뢰를 제공하는 것이다. 이러한 목표를 달성하려면, 시스템의 설계, 사용후핵연료로부터의 잔류 열을 제거하고 방사선 차폐를 제공함과 동시에 설계 기준에 지정된 시스템의 수명동안 격납을 유지하기 위한 기능을 포함한다. 운영 중 발생가능한 설계사항은 설계 기준에 반영되어야 한다. 본 논문에서는 건식저장시스템의 일반적인 성능 요구 사항을 소개하였다. 저장시스템은 인허가를 위한 규제 요구사항과 연관하여 사용후핵연료를 저장할 수 있도록 설계된다. 여기서 최대연소도의 증가는 냉각기간과 맞물려 가감할 수 있다. 이때 열부하와 방사능의 크기가 최대 설계기준 연소도의 기준을 설정하는 주요한 인자가 된다. 이외에 건식저장시스템의 설계기준사고와 다른 분야 즉 기계 및 구조 그리고 차폐 및 방사선적인 요구사항들의 종류가 기술되었다. Safe operation and maintenance of engineered dry storage systems for spent fuel from nuclear power plants basically depends on adequately adopted design requirements. The most important design target of the system are those which provide the necessary assurances that spent fuel can be received, handled, stored and retrieved without undue risk to health and safety of workers and the public. To achieve these objectives, the design of the system incorporates features to remove spent fuel residual heat, to provide for radiation protection, and to maintain containment over the lifespan of the system as specified in the design specifications. The features also provide for all possible anticipated operational occurrences and design basis events in accordance with the design basis as guided by the designated regulations. The general performance requirements of a projected storage system are introduced in this paper. The storage system is designed to store fuel assemblies in associated with designated regulatory requirements. Small increases/decreases in maximum burnup can be adjusted with cooling time. These variations are compensated for by a corresponding small site-specific increase/decrease in the design basis-cooling period, as long as the maximum heat load and radioactivity of loaded fuel assemblies are met. Generic design basis events considered for the storage system are summarized. Shielding and radiological requirements along with mechanical and structural are derived in this study.

외래환자 대상 당뇨병 약료서비스 모델 개발

윤정현,Yoon, Jeong-Hyun 한국임상약학회 2017 한국임상약학회지 Vol.27 No.1

The prevalence of diabetes and its related morbidity and mortality are being increased. Despite the advancement of evidence-based pharmacotherapy in the management of diabetes, many patients in our country do not achieve satisfied therapeutic outcomes. Pharmaceutical care service can be defined as a patient-centered clinical service provided by pharmacists to improve therapeutic outcomes and quality of life of patients, by identifying, and preventing or resolving drug-related problems (DRPs). Pharmaceutical care service is interdisciplinary team-based practice, and is provided through collaborative practice agreement (CPA) between one or more physicians and pharmacists. This article describes a model of pharmaceutical care service which can be adopted in our country for patients with diabetes in the ambulatory care settings. With the successful implementation of this service, clinical, economic, and humanistic outcomes of patients will be improved. Therefore, by actively implementing pharmaceutical care service, pharmacist should contribute to the promotion of patients' health and to the advancement of health care delivery system.

최적신뢰성에 의한 강합성 복합사장교의 확률적 위험도평가

윤정현,조효남,Yoon, Jung Hyun,Cho, Hyo Nam 한국강구조학회 2007 韓國鋼構造學會 論文集 Vol.19 No.4

Probabilistic risk assessment was conducted on a hybrid cable-stayed bridge consisting of a steel-composite plate girder and a concrete girder with a long span, designed using the working stress design and strength design methods. The component reliabilities of the bridge's cables, pylons, girders, and steel-concrete conjunction were evaluated using the AFOSM(Advanced First Order Second Moment) algorithm and the simulation technique at the critical sections, based on the maximum axial force, shear, and positive and negative moments of the selected sections. For the analysis of system reliability, the hybrid cable-stayed bridge consisting of cables, pylons, and plate girders was modeled into combined failure modes, and for system reliability, the probabilities of failure and reliability index of the structural system were evaluated. Based on the results of this study, the critical failure modes of the hybrid cable-stayed bridge based on the bridge's structural characteristics are suggested, and the efficiency of the partial ETA technique for use in the risk assessment method was confirmed. 허용응력설계법과 강도설계법으로 설계된 강합성 플레이트 보강형과 콘크리트 보강형으로 구성된 장대교량인 복합사장교의 확률적 위험도 평가를 수행하였다. 최대 축력, 전단력 및 정 부모멘트 발생단면에 기초한 위험단면에 대해 AFOSM 알고리즘과 시뮬레이션기법을 사용하여 케이블, 주탑, 보강형 및 강-콘크리트 접합부의 요소신뢰성을 평가하였다. 체계신뢰성해석을 위해, 케이블, 주탑 및 콘트리트와 강합성 보강형으로 구성된 복합사장교의 시스템을 조합 파괴모드로 모델링하였으며, 이를 통해 전체 구조시스템의 파괴확률과 신뢰성지수를 산출하였다. 본 연구를 통해 복합사장교의 거동특성에 기초한 파괴모드를 제안하였고 위험도평가 방법으로서 부분 ETA기법의 효용성을 확인하였다.

FCM과 FSM공법에 의한 강-콘크리트 복합사장교의 신뢰성에 기초한 시공간 구조안전도평가

윤정현,조효남,Yoon, Jung Hyun,Cho, Hyo Nam 한국강구조학회 2007 韓國鋼構造學會 論文集 Vol.19 No.5

본 연구에서는 시공간의 구조안전도 확보와 교량붕괴를 방지하기 위해 FCM과 FSM공법으로 가설되는 강-콘크리트 복합사장교의 안전도평가 모형을 제안하였다. 구조물의 저항과 하중효과에 내제된 각종 불확실성을 합리적으로 고려하는 구조신뢰성이론에 의해 강합성거더와 콘크리트거더가 연결된 강-콘크리트 복합사장교의 저항과 하중의 분포특성을 정의하고 가설중 영구구조물과 가설구조물의 강도한계상태방정식을 제안하였다. 케이블, 주탑, 거더, 강-콘크리트 접합부 및 가설벤트의 신뢰성해석을 위해 AFOSM 알고리즘과 MCS 기법을 사용하였다. 또한, 가설단계별 구조시스템에 따라 요소신뢰성해석을 수행하였다. 제안된 평가모형의 타당성과 실용성을 검증하기 위하여 제시된 방법을 실제 교량에 적용하였다. 유사한 교량의 안전도 관리를 위한 중점 항목을 정의하기 위해서 주요 인자에 대한 민감도 분석이 수행되었다. 본 연구를 통해, 제안된 모형은 FCM과 FSM으로 가설되는 강-콘크리트 복합사장교의 시공간 안전도 평가를 위한 합리적이고 실용적인 방법으로 적용될 수 있을 것으로 판단되었다. In this study, the models and methods for the safety assessment of Steel-Concrete Hybrid Cable-Stayed Bridge, which consists of steel composite girder and concrete girder erected by the FCM(Free Cantilever Method) and FSM(Full Staging Method) are proposed for the assurance of structural safety and the prevention against bridge collapse during construction. By the structural reliability approach that reasonably considers the uncertainties associated with the resistance and the load effect, the resistance and the load distribution characteristics of Steel-Concrete Hybrid Cable-Stayed Bridgeare defined and the strength limit state equations of permanent structures and temporary structures during construction are suggested. An AFOSM algorithm and MCS technique are used for the reliability analysis of cables, pylons, girders, steel-concrete conjunction part and temporary bents. Also, component reliability analyses are performed at the construction stages based on the structural system model. To demonstrate their rationality and practicality, the proposed models and approaches are applied to a real bridge. The sensitivity analyses of main parameters are performed in order to identify the critical factors that control the safety of similar bridges. As a result, it may be stated that the proposed models could be implemented as a rational and practical approach for the safety assessment of Steel-Concrete Hybrid Cable-stayed bridges erected by FCM and FSM during construction.

KSC-7 사용후핵연료 수송용기 핵임계해석

윤정현,최종락,곽은호,이흥영,정성환,Yoon, Jung-Hyun,Choi, Jong-Rak,Kwak, Eun-Ho,Lee, Heung-Young,Chung, Sung-Whan 대한방사선방어학회 1993 방사선방어학회지 Vol.18 No.2

본 연구에서는 사용후핵 연료를 안전하게 수송할 수 있는 수송용기의 여러 가지 설계 항목중에 수송용기 내부에 장전한 핵연료에 의한 핵임계반응을 방지하기 위한 핵임계해석을 수행하였다. 핵임계 해석에 사용한 HANSEN-ROACH-KENO-Va 전산시스템에 대한 검증계산을 수행하였고 수송용기의 핵임계측면에서의 안전성을 확보하기 위해 가능한 보수적인 가정을 하여 어떠한 경우에도 수송용기에 장전된 핵연료가 임계상태에 도달하지 않도록 수송용기 내부의 구조 및 적절한 핵임계 방지제를 선택하였고 정상수송 및 가상사고 조건 등에 대한 해석을 수행하였다. 그 결과 KSC-7 수송용기 의 설계조건을 만족하고 핵임계측면에서의 안전성을 보장할 수 있는 재료 및 구조에 대한 결론을 해석적으로 도출하였다. The criticality of the shipping cask(KSC-7) for transportion of 7PWR spent fuel assemblies has been calculated and analysised on the basis of neutron transport theory. For criticality analysis, effects of the rod pitches, the fixed neutron absorbers(borated sus+boral) were considered. The effective multiplication factor has been calculated by KENO-Va, Mote Carlo method computer code, with the HANSEN-ROACH 16 group cross section set, which was made for personal computer system. The criticality for the KSC-7 cask was calculated in terms of the fresh fuel which was conservative for the aspects of nuclear critility. From the results of criticality analysis, the calculated Keff is proved to be lower than subcritical limit during normal transportation and under hypothetical accident condition. The maximum calculated criticalities of the KSC-7 were lower the safety criticality limit 1.0 recommended by US 10CFR71 both under normal and hypothetical accident condition. Also, to verify the KSC-7 criticality calculation results by using KENO-Va, it was carried out benchmark calculation with experimental data of B & W(Bobcock and Wilcox) company. From the 3s series of calculation of the KSC-7 cask and benchmark calculation, the cask was safely designed in nuclear criticality, respectively.

연구논문 : 인적자원관리관행에 대한 공정성 인식과 조직유효성간의 관련성에 관한 연구 -조직몰입의 매개효과검증을 중심으로-

윤정현 ( Jung Hyun Yoon ),이재훈 ( Jae Hoon Rhee ),김기근 ( Ki Keun Kim ) 한국인적자원관리학회 2010 인적자원관리연구 Vol.17 No.3

[화학] HPLC에 의한 꿀 중의 당조성 분석과 화학계량학적 고찰

윤정현(Jung-Hyeon Yoon),배선영(Sun-Young Bae),김건(Kun Kim),이동선(Dong-Sun Lee) 한국분석과학회 1997 분석과학 Vol.10 No.5

방문 지도교사의 감성지능과 조직유효성 간의 관련성: 자기효능감의 조절효과를 중심으로

윤정현 ( Jung Hyun Yoon ),조외출 ( Oi Chul Cho ) 국민대학교 사회과학연구소 2010 社會科學硏究 Vol.23 No.1

2007 강구조 기술발표회

윤정현(Jung Hyun Yoon) 한국강구조학회 2007 韓國鋼構造學會誌 Vol.19 No.4