Comparison of Thermal and Mechanical Responses of the Three Mile Island Unit 2 Reactor Vessel

Author:

Thinnes Gary L.1,Moore Richard L.1

Affiliation:

1. Idaho National Engineering Laboratory, EG&G Idaho, Inc. P.O. Box 1625, Idaho Falls, Idaho 83415-3503

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference5 articles.

1. G. L. THINNES, “TMI-2 Lower Head Creep Rupture Analysis,” EGG-TMI-8133, EG&G Idaho, Inc. (Aug. 1988).

2. E. C. LEMON, “COUPLE/FLUID, A Two-Dimensional Finite Element Thermal Conduction and Convection Code,” ISD-SCD-80-1, EG&G Idaho, Inc. (Feb. 1980).

3. ABAQUS User’s Manual, Version 4.6, Hibbitt, Karlsson & Sorensen, Inc. Providence, Rhode Island (1987).

4. G. V. SMITH, “Evaluations of the Elevated Temperature Tensile and Creep-Rupture Properties of C-Mo, Mn-Mo, and Mn-Mo-Ni Steels,” DS47, Metal Properties Council, American Society for Testing and Materials ASTM Data Series Publication (1971).

5. G. B. REDDY and D. J. AYRES, “High Temperature Elastic-Plastic and Creep Properties for SA533 Grade B Class 1 and SA508 Materials,” NP-2763, Electric Power Research Institute (Dec. 1982).

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