• 제목/요약/키워드: nuclear testing

검색결과 706건 처리시간 0.039초

약물부하 검사법의 현재와 미래 (Current Trends and Future Development in Pharmacologic Stress Testing)

  • 배진호;이재태
    • 대한핵의학회지
    • /
    • 제39권2호
    • /
    • pp.107-113
    • /
    • 2005
  • Pharmacologic stress testing for myocardial perfusion imaging is a widely used noninvasive method for the evaluation of known or suspected coronary artery disease. The use of exercise for cardiac stress has been practiced for over 60 years and clinicians are familial with its using. However, there are inevitabe situations in which exorcise stress is inappropriate. A large number of patients with cardiac problems are unable to exercise to their full potential due to comorbidity such as osteoarthritis, vascular disease and pulmonary disease and a standard exercise stress test for myocardial perfusion imaging is suboptimal means for assessment of coronary artery disease. This problem has led to the development of the pharmacologic stress test and to a great increase in its popularity. All of the currently used pharmacologic agents have well-documented diagnostic value. This review deals the physiological actions, clinical protocols, safety, nuclear imaging applications of currently available stress agents and future development of new vasodilating agents.

Detectability evaluation of the loose parts in steam generator by eddy current testing techniques

  • Kim, Kyungcho;Min, Kyongmahn;Kim, Changkuen;Kim, Jin-Gyum;Jhung, Myungjo
    • Nuclear Engineering and Technology
    • /
    • 제50권7호
    • /
    • pp.1160-1167
    • /
    • 2018
  • Detectability of the loose parts (LPs) in steam generator (SG) was studied with eddy current testing technique such as X-probe, bobbin and rotating coils ($MRPC^{(R)}$) as a function of LP size and spacing between LP and tube or between LP and support structures. SG mockup simulating SG tube and support structures with LP was fabricated. The X-probe showed slightly better detectability than $MRPC^{(R)}$ for LP of ferrous (F-LP) material and vice versa for LP of nonferrous (NF-LP) material. In terms of feasibility, inspection rate and other predictable features of the SG tubing inspections, X-probe can be used reliably for monitoring the LPs and the flaws formed by LPs on SG tubes.

IRRADIATION DEVICE FOR IRRADIATION TESTING OF COATED PARTICLE FUEL AT HANARO

  • Kim, Bong Goo;Park, Sung Jae;Hong, Sung Taek;Lee, Byung Chul;Jeong, Kyung-Chai;Kim, Yeon-Ku;Kim, Woong Ki;Lee, Young Woo;Cho, Moon Sung;Kim, Yong Wan
    • Nuclear Engineering and Technology
    • /
    • 제45권7호
    • /
    • pp.941-950
    • /
    • 2013
  • The Korean Nuclear-Hydrogen Technology Development (NHTD) Plan will be performing irradiation testing of coated particle fuel at HANARO to support the development of VHTR in Korea. This testing will be carried out to demonstrate and qualify TRISO-coated particle fuel for use in VHTR. The testing will be irradiated in an inert gas atmosphere without on-line temperature monitoring and control combined with on-line fission product monitoring of the sweep gas. The irradiation device contains two test rods, one has nine fuel compacts and the other five compacts and eight graphite specimens. Each compact contains about 260 TRISO-coated particles. The irradiation device is being loaded and irradiated into the OR5 hole of the in HANARO core from August 2013. The device will be operated for about 150 effective full-power days at a peak temperature of about $1030^{\circ}C$ in BOC (Beginning of Cycle) during irradiation testing. After a peak burn-up of about 4 atomic percentage and a peak fast neutron fluence of about $1.7{\times}10^{21}\;n/cm^2$, PIE (Post-Irradiation Examination) of the irradiated coated particle fuel will be performed at IMEF (Irradiated Material Examination Facility). This paper reviews the design of test rod and irradiation device for coated particle fuel, and discusses the technical results for irradiation testing at HANARO.

안전등급 컴퓨터, 노심보호계산기계통 설계 (Safety Computer System, CPCS Design in Nuclear Power Plant)

  • Sohn, Se-Do;Young Suh;Kang, Byung-Heon;Shin, Ji-Tae;Chun, Chong-Son
    • Nuclear Engineering and Technology
    • /
    • 제26권4호
    • /
    • pp.502-506
    • /
    • 1994
  • 안전등급 컴퓨터계통 설계에 대해서 노심보호계산기계통 소프트웨어 설계와 검증시험을 중심으로 살펴보았다. 안전계통에 컴퓨터계통을 사용하면, 하드웨어뿐만 아니라 소프트웨어에 대한 철저한 검중시험이 요구된다. 노심보호계산기계통에 대한 검증시험은 두개의 소프트웨어 버전을 개발하여, 수행결과를 서로 비교함으로써 수행된다. 하나는 어셈블리언어로, 또 다른 하나는 포트란으로 구현된다. 검증시험은 순차적이고 중첩되게 수행된다. 일차 시험은 모든 브랜치 루틴을 수행하여 각 소프트웨어 모듈이 바르게 구현되었음을 확인하는 작업이다. 이차 시험은 통합된 소프트웨어가 모든 요건을 만족하는가 그리고 시간요건을 만족하는 지를 검증한다. 이러한 철저한 검증시험을 통해서 영광 3, 4호기 노심보호계산기계통이 올바르고 완벽하게 구현되어 요건서를 만족함이 확인되었다.

  • PDF

원전 증기발생기 세관 검사를 위한 와전류 탐상 프로브의 현황 및 전망 (Present Condition and View of Eddy Current Testing Probe for Nuclear Power Plant Steam Generator Tube Examination)

  • 김지호;이향범
    • 한국정보통신설비학회:학술대회논문집
    • /
    • 한국정보통신설비학회 2006년도 하계학술대회
    • /
    • pp.241-245
    • /
    • 2006
  • In the examination of Steam Generator (SG) tube in Nuclear Power Plant (NPP) Eddy Current Testing (ECT) probes play an Important role in detecting the defects. Bobbin probe and Rotating Pancake Coil (RPC) probe is usually used for the inspection of SG tube. Bobbin probe is good at high speed inspection, but ability of detection of circumferential defect is very weak. On the contrary RPC probe, which moves for inspection in the direction of axial and circumferential simultaneously, has very slow inspection speed, but it was excellent detection capability fur small cracks, which is hardly detected by bobbin probe. Many examinations of SG tube examination of NPP are achieved during short period. Therefore, solution about this must develop probe of new form for examination performance and examination time shortening of other probe. In this paper, analyzed technological present condition of Bob-bin probe and RPC probe been using in Nondestructive Testing (NDT) for SG tube defect detection and Appeared about background theory and view of developed probe newly.

  • PDF

원자력 발전소 STUD BOLT의 자동초음파 주사장치 개발 (Development of Automatic Ultrasonic Testing Equipment for Pressure-Retaining Studs and Bolts in Nuclear Power Plant)

  • 서동만;박문호;홍순신
    • 비파괴검사학회지
    • /
    • 제9권1호
    • /
    • pp.106-110
    • /
    • 1989
  • Bolting degradation problems in primary coolant pressure boundary applications have become a major concern in the nuclear industry. In the bolts concerned, the failure mechanism was either corrosion wastage(loss of bolt diameter) or stress-corrosion cracking.(3) Here the manual ultrasonic testing of RPV(Reactor Pressure Vessel) and RCP(Reactor Coolant Pump) stud has been performed. But it is difficult to detect indications because examiner can not exactly control the rotation angle and can not distinguish the indication from signals of bolt. In many cases, the critical sizes of damage depth are very small(1-2 mm order). At critical size, the crack tends to propagatecompletly through the bolt under stress, Resulting in total fracture.(3) Automatic stud scanner for studs(bolts) was developed because the precise measurement of bolt diameter is required in this circumstance. By use of this scanner, the rotation angle of probe was exactly controlled and the exposure time of radiations was reduced.

  • PDF