Development of the guideline on inelastic analysis for design

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

Volumn 472, Issue , 2004, Pages 53-60

  Tanaka, Yoshihiko ^a   Shibamoto, Hiroshi ^a   Inoue, Kazuhiko ^a   Kasahara, Naoto ^b   Ando, Masanori ^b   Morishita, Masaki ^b  

^a Mitoshiro Bldg   (Japan)

^b JAPAN ATOMIC ENERGY AGENCY   (Japan)

Author keywords

[No Author keywords available]

Indexed keywords

CREEP FATIGUE; INELASTIC ANALYSIS; NUCLEAR DESIGN; STRAIN RANGES;

ACCIDENT PREVENTION; ELASTICITY; LOADS (FORCES); MATHEMATICAL MODELS; STANDARDS; STRAIN; STRUCTURAL DESIGN;

FAST REACTORS;

EID: 7644234075     PISSN: 0277027X     EISSN: None     Source Type: Conference Proceeding    
DOI: 10.1115/PVP2004-2259     Document Type: Conference Paper

References (7)

1. Y. Sagayama et al: "Overall Plan and Progress Situation of "The Feasibility Study on Commercialized FR Cycle Systems", GLOBAL 2003
2. N. Kasahara et al: "Research and Development plans for Fast Reactor Structural Design Standard (FDS)", this proceeding
3. C.E. Pugh, "Currently Recommended Constitutive Equations for Inelastic Analysis for FFTF Components", ORNL-TM-3602, Oak Ridge National Laboratory, 1972
4. J. M. Corum, "Interim Guidelines for Detailed Inelastic Analysis of High Temperature Reactor System Components", ORNL-5014, Oak Ridge National Laboratory, 1974
5. PNC Design Standard Working Group, "Guidelines for Design of Fast Reactor System Components", PNC SN 9410 86-132, Japan Nuclear Fuel Cycle Development Institute, 1986 (in Japanese)
6. Takahashi, Y., "Advancement of High-Temperature Structural Design Method for Fast Reactor Components Part II: Inelastic Constitutive Model for 316FR", ASME Book No. H01146, 1998, pp. 167-174.
7. N. Kawasaki et al: "Recent Design Improvement of Elevated Temperature Structural Design Guide for DFBR in Japan", 15th SMiRT, Vol. IV (1999) p.161