• Title/Summary/Keyword: 일체형원자로

Search Result 79, Processing Time 0.027 seconds

A Software Testing Plan for Integral Reactor MMIS Design (일체형원자로 MMIS 설계에 적용을 위한 소프트웨어 시험 계획)

  • Suh, Yong-Suk;Hur, Seop;Park, Geun-Ok;Lee, Jong-Bok;Kim, Dong-Hoon
    • Proceedings of the Korea Information Processing Society Conference
    • /
    • 2001.04b
    • /
    • pp.1097-1100
    • /
    • 2001
  • 소프트웨어 개발자로부터 독립된 소프트웨어 시험자가 수행하는 소프트웨어 시험은 소프트웨어의 안전성 향상을 위해 필요하다. 컴퓨터기반의 디지틀시스템으로 설계되는 일체형원자로 MMIS에 적용하기 위한 소프트웨어 시험 계획을 개발할 필요가 있다. 본 논문은 소프트웨어 시험 계획을 소프트웨어시험 조직 구성, 시험 문서, 시험 절차, 시험 방법을 중심으로 제시한다. 소프트웨어 시험 방법은 원시코드 정적분석과 동적시험을 구분하여 기술한다. 본 논문에서 제시된 소프트웨어 시험 계획은 원자력 규제기관에서 요구하는 소프트웨어 시험 요구사항을 만족한다. 본 논문을 통해 제시된 소프트웨어 시험 계획을 일체형원자로 MMIS 소프트웨어 개발 시 적용하여 소프트웨어 고장율 데이터를 수집할 예정이다.

  • PDF

Development of Position Indicator for System-Integrated Reactor SMART (일체형원자로 SMART의 제어봉 위치지시기 개발)

  • Yu, Je-Yong;Kim, Ji-Ho;Huh, Hyung;Kim, Jong-In;Chang, Moon-Hee
    • Proceedings of the KSME Conference
    • /
    • 2001.06d
    • /
    • pp.921-926
    • /
    • 2001
  • The reliability and accuracy of the information on control rod position are very important to the reactor safety and the design of the core protection system. In this study, a thorough investigation on the RSPT(Reed Switch Position Transmitter) type control rod position indication system and its actual implementation in the exiting nuclear power plants in Korea was performed first. A design of the control rod position indication system using reed switch for the CEDM on the system-integrated reactor SMART was developed based on the position indicator technology identified through the investigation. The feasibility of the design was evaluated by test of manufactured control rod position indicator using reed switch for SMART.

  • PDF

Qualification Test of Main Coolant Pump for an Integral Type Reactor (일체형원자로 주냉각재펌프의 검증시험)

  • Park, Sang-Jin;Yoon, Eui-Soo;Heo, Pil-Woo;Kim, Duck-Jong;Oh, Hyoung-Woo
    • 유체기계공업학회:학술대회논문집
    • /
    • 2005.12a
    • /
    • pp.509-514
    • /
    • 2005
  • Main coolant pump (MCP) is a canned-motor-type axial pump to circulate the primary coolant between nuclear fuel rods and steam generators in an integral type reactor. The reactor is designed to operate under condition of 310 oC and 14.7 MPa. Thus MCP has to be tested under same operating condition as reactor design condition in order to verify its performance and safety. In present work, a test loop to simulate real operating situation of the reactor has been designed and constructed to test MCP. And then, as a part of qualification test, canned motor functional test and pump hydraulic performance test have been carried out upon a prototype MCP. Canned motor efficiency and pump hydraulic characteristics including homologous curves and NPSH curves were obtained from the qualification test.

  • PDF