• Title/Summary/Keyword: 중성자 도시메트리

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Neutron Fluence Evaluation for Reactor Pressure Vessel Using 3D Discrete Ordinates Transport Code RAPTOR-M3G (3차원 수송계산 코드(RAPTOR-M3G)를 이용한 원자로 압력용기 중성자 조사량 평가)

  • Maeng, Young Jae;Lim, Mi Joung;Kim, Byoung Chul
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.10 no.1
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    • pp.107-112
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    • 2014
  • The Code of Federal Regulations, Title 10, Part 50, Appendix H requires surveillance program for reactor pressure vessel(RPV) that the peak neutron fluence at the end of the design life of the vessel will exceed $1.0E+17n/cm^2$ (E>1.0MeV). 2D/1D Synthesis method based on DORT 3.1 transport calculation code has been widely used to determine fast neutron(E>1.0MeV) fluence exposure to RPV in the beltline region. RAPTOR-M3G(RApid Parallel Transport Of Radiation-Multiple 3D Geometries) performing full 3D transport calculation was developed by Westinghouse and KRIST(Korea Reactor Integrity Surveillance Technology) and applied for the evaluations of In-Vessel and Ex-Vessel neutron dosimetry. The reaction rates from measurement and calculation were compared and the results show good agreements each other.