Verification of alternative criteria for shakedown evaluation using 2-dimensional and 3-dimensional nozzle models

American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP

Volumn 439, Issue , 2002, Pages 23-30

  Asada, Seiji ^a   Okamoto, Asao ^a   Nishiguchi, Isoharu ^a  

^a MITSUBISHI HEAVY INDUSTRIES LTD   (Japan)

Author keywords

[No Author keywords available]

Indexed keywords

MILLER'S THEORETICAL ANALYSIS;

ELASTIC MODULI; FINITE ELEMENT METHOD; NOZZLES; PLASTICITY; THERMAL STRESS;

PRESSURE VESSELS;

EID: 0036383555     PISSN: 0277027X     EISSN: None     Source Type: Conference Proceeding    
DOI: 10.1115/PVP2002-1218     Document Type: Conference Paper

References (10)

1. Okamoto, A. et al., 2001, "Recent advancement on the draft of Japanese stress evaluation criteria based on partial inelastic analyses" ASME PVP Vol.419 pp.17-24.
2. Nishiguchi, I. et al., 2002, "Analytical and numerical evaluation of the cyclic yield area for shakedown requirements" to be published in 2002 ASME PVP Conference.
3. Yamamoto, Y. et al., 2001, "Verification of alternative stress evaluation criteria and the code elastic limits for primary plus secondary stress" ASME PVP Vol.419 PP.25-32.
4. Yamamoto, Y. et al., 2002, "Evaluation of thermal stress ratchet in plastic FEA" to be published in 2002 ASME PVP Conference.
5. ASME, 2001, Boiler and Pressure Vessel Code Sec.III, Division 1, "Rules for Construction of Nuclear Power Plant Components", ASME, New York.
6. Asada, S. et al., 2002, "Verification of alternative criteria for shakedown evaluation using flat head vessel" to be published in 2002 ASME PVP Conference.
7. Asada, S. et al., 2001, "Evaluation of conservativism tin the simplified elastic-plastic analysis using analytical results - Part 2: Proposal of a new Ke-function" ASME PVP Vol.419 PP.33-42
8. Miller, D. R., 1959, "Thermal-stress ratchet mechanism in pressure vessels", Journal of Basic Engineering, June 1959, ASME.
9. Kalnins, A., 2001, "Shakedown check for pressure vessels using plastic FEA" ASME PVP Vol.419 pp.9-16
10. MITI Notification No.501, "Technical standards for construction of nuclear power plant components", 1994, Japan.