Advanced Gas-Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress Report, April 1, 1983-June 30, 1983

摘要

Objectives are to evaluate candidate alloys for very high temperature reactor (VHTR) applications, particularly nuclear process heat (NPH) applications, in terms of the effects of simulated reactor primary coolant (helium containing small amounts of various other gases), high temperatures, and long time exposure on the mechanical properties and structural and surface stability. A second objective is to select and recommend materials for future test facilities and more extensive qualification programs and to develop the critical high temperature materials data needed for the design of major system components, especially those in the primary coolant circuit. Work covered in this report includes the activities associated with modifications and operation of the simulated reactor helium supply system and testing equipment. Progress on the multispecimen creep testing extensions to 15,000 hours is discussed. The status of creep rupture testing in simulated HTGR helium and in air is covered. The status of fatigue testing in simulated HTGR helium is described; the test results obtained are listed and discussed. Status of materials and testing work is presented. (ERA citation 09:004630)