Published 1991 | Version v1
Book

Rules for design of alloy 617 nuclear components to very high temperatures

  • 1. Oak Ridge National Lab., TN (United States)

Description

Very-high-temperature gas-cooled reactors provide attractive options for electric power generation using a direct gas-turbine cycle and for process-heat applications. For the latter, temperatures of at least 950 degrees C are desirable. As a first step to providing rules for the design of nuclear components operating at very high temperatures, a draft ASME Boiler and Pressure Vessel Code Case has been prepared by an ad hoc Code task force. The Case, which is patterned after the high-temperature nuclear Code Case N-47, covers Ni-Cr-Co-Mo Alloy 617 for temperatures to 982 degrees C. The purpose of this paper is to provide a synopsis of the draft Case and the significant differences between it and Case N-47. Particular emphasis is placed on the material behavior and allowables. The paper also recommends some materials and structures development activities that are needed to place the design methodology on a sound and defensible footing

Additional details

Publishing Information

Publisher
American Society of Mechanical Engineers.
Imprint Place
New York, NY (United States)
ISBN
0-7918-0810-6
Imprint Title
Fatigue, fracture, and risk 1991
Imprint Pagination
210 p.
Journal Page Range
p. 147-154.

Conference

Title
1991 American Society of Mechanical Engineers (ASME) pressure vessels and piping conference.
Dates
23-27 Jun 1991.
Place
San Diego, CA (United States).

Optional Information

Secondary number(s)
CONF-910602--.