Structural Engineering and Mechanics

  • 제14권2호
  • /
  • Pages.191-208
  • /
  • 2002
  • /
  • 1225-4568(pISSN)
  • /
  • 1598-6217(eISSN)
테크노프레스 (Techno-Press)
권호 표지
DOI QR코드

DOI QR Code

Pressure-temperature limit curve for reactor vessel evaluated by ASME code

  • 투고 : 2001.06.29
  • 심사 : 2002.05.20
  • 발행 : 2002.08.25
⟨ 이전 논문 다음 논문 ⟩

초록

A comparative assessment study for a generation of the pressure-temperature (P-T) limit curve of a reactor vessel is performed in accordance with ASME code. Using cooling or heating rate and vessel material properties, 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 reactor cool-down and heat-up. P-T limit curves are analyzed with respect to defect orientation, clad thickness, toughness curve, cooling or heating rate and neutron fluence. The resulting P-T curves are compared each other.

키워드

참고문헌

  1. ASME. (1998a), ASME Boiler and Pressure Vessel Code, Section III Rules for Construction of Nuclear Power Plant Components, Appendix G Protection against Nonductile Failure, The American Society of Mechanical Engineers.
  2. ASME. (1998b), ASME Boiler and Pressure Vessel Code, Section XI Rules for Inservice Inspection of Nuclear Power Plant Components, Appendix G Fracture Toughness Criteria for Protection against Failure, The American Society of Mechanical Engineers.
  3. ASME. (1998b), ASME Boiler and Pressure Vessel Code, Section XI Rules for Inservice Inspection of Nuclear Power Plant Components, Appendix G Fracture Toughness Criteria for Protection against Failure, The American Society of Mechanical Engineers.
  4. EPRI. (1996), "P-T calculator for window Ver. 1.0", Electric Power Research Institute.
  5. Glasstone, G. (1960), Principles of Nuclear Reactor Engineering, D.Van Nostrand Co., New Jersey.
  6. Holman, J.P. (1981), Heat Transfer, McGraw-Hill, London.
  7. Myers, G.E. (1971), Analytical Method in Conduction Heat Transfer, McGraw-Hill, New York.
  8. Oezisik, M.N. (1980), Heat Conduction, John Wiley & Sons, New York.
  9. Timoshenko, S.P. and Goodier, J.M. (1970), Theory of Elasticity, McGraw-Hill, New York.
  10. USNRC. (1988), "Radiation embrittlement of reactor vessel materials", Regulatory Guide 1.99, Rev.2, US Nuclear Regulatory Commission, May.
  11. USNRC. (1996), "Fracture toughness requirements for protection against pressurized thermal shock events", 10 CFR 50.61, US Nuclear Regulatory Commission, May.

피인용 문헌

  1. Determination of Pressure-Temperature Limit Curves Using Deterministic and Probabilistic Approaches vol.306-308, pp.1662-9795, 2006, https://doi.org/10.4028/www.scientific.net/KEM.306-308.333
  2. Evaluation of P-T Limit Curves According to Alternative Fracture Toughness Requirements vol.1051, pp.1662-8985, 2014, https://doi.org/10.4028/www.scientific.net/AMR.1051.896