Experimental stress analysis of a nuclear-reactor pressure vessel

Author:

Greenstreet B. L.,Witt F. J.,Smith J. E.,Maxwell R. L.,Shobe L. R.

Publisher

Springer Science and Business Media LLC

Subject

Mechanical Engineering,Mechanics of Materials,Aerospace Engineering

Reference6 articles.

1. “Experimental Gas-Cooled Reactor Final Hazards Summary Report,” I, USAEC Report ORO-586, Oak Ridge Operations Office, Oct. 10, 1962.

2. Greenstreet, B. L., et al., “Experimental Stress Analysis of EGCR Pressure Vessel,” USAEC Report ORNL-3157, Oak Ridge National Laboratory, Nov, 14, 1961.

3. “Gas-Cooled Reactor Project Quarterly Progress Report June 30, 1961,” USAEC Report ORNL-3166, Oak Ridge National Laboratory, 39–40.

4. Timoshenko, S. and Woinowsky-Krieger, S., Theory of Plates and Shells, McGraw-Hill Co., Inc., 2nd ed. 466–471 and 481–485 (1959).

5. “Gas-Cooled Reactor Project Quarterly Progress Report Sept. 30, 1960, USAEC Report ORNL-3015, Oak Ridge National Laboratory, 42–47.

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