Nuclear Engineering and Technology

  • 제33권5호
  • /
  • Pages.498-513
  • /
  • 2001
  • /
  • 1738-5733(pISSN)
  • /
  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
권호 표지

Pressure-Temperature Limit Curve of Reactor Vessel by ASME Code Section III and Section XI

  • M.J. Jhung (Korea Institute of Nuclear Safety) ;
  • Kim, S.H. (Korea Institute of Nuclear Safety) ;
  • Lee, T.J. (Korea Institute of Nuclear Safety)
  • 발행 : 2001.10.01
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초록

Performed here is a comparative assessment study for the generation of the pressure- temperature (P/T) limit curve of the reactor vessel. Using the cooling or heating rate and vessel material properties, the stress distribution is obtained to calculate stress intensity factors, which are compared with the material fracture toughness to determine the relations between operating pressure and temperature during cool-down and heat-up. P/T limit curves are generated with respect to crack direction, clad thickness, toughness curve, cooling or heating rate and neutron fluence, and their results are compared.

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참고문헌

  1. ASME, ASME Boiler and Pressure Vessel Code,Rules for Construction of Nuclear Power Plant Components, Appendix G Protection aganist Nonductile Failure, The American Society of Mechanical Engineers (1998)
  2. ASME, ASME Boiler and Pressure Vessel Code,Rules for Inservice Inspection of Nuclear Power Plant Components, Appendix G Fracture Toughness Criteria for Protection against Failure, The American Society of Mechanical Engineers (1998)
  3. ASME, ASME Boiler and Pressure Vessel Code, Section XI Code Case N-640, 'Alternative Reference Fracture Toughness for Development of P-T Limit Curves,' The American Society of Mechanical Engineers (1998)
  4. USNRC, 'Fracture Toughness Requirments for Protection against Pressurized Thermal Shock Events,' 10 CFR 50.61, US Nuclear Regulatory Commission, May (1998)
  5. USNRC, 'Radiation Embrittlement of Reactor Vessel Materials,' Regulatory Guide 1.99 Rec.2, US Nuclear Regulatory Commission, May (1988)
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  10. Timoshenko, S.P., Goodier, J.M., Theory of Elasticity, McGraw-Hill, New York (1970)
  11. Lee, T.J., Choi, J.B., Kim, Y.J., Park, Y.W., Jhung, M.J., 'Development of a RViES system for reactor vessel integrity evaluation,' Transactions of the Korean Society of Mechanical Engineering (A), Vol.24, No.8, pp.2083-2090 (2000)
  12. EPRI, 'P-T Calculator for Window Ver. 1.0,' Electric Power Research Institute (1996)