Codes and standards for U.S. Department of Energy heavy water-new production reactor
Description
The United States Department of Energy is designing a new generation of production reactors that will replace the aging production reactors at the Savannah River Site in Aiken, South Carolina. A heavy water reactor is one of the options being pursued during the Title I design phase. The increases in understanding and the vast experiences gained form existing production reactors and commercial nuclear power plants have led to proposed improvements in several areas of the design for the Heavy Water-New Probation Reactor (HW-NPR). Technical advances and ASME Boiler and Pressure Vessels Code Cases, that reflect the increases in experience and understanding are the basis for many of the proposed changes presented in this paper. Among the proposed areas of change presented in this chapter are: the implications of designing for a 60-year plant life; designing the ensure material and system integrity of the plant; means to assess fatigue damage to the pressurizer surge lines; the application of leak-before-break evaluation to piping and components; and the development of seismic criteria for the HW-NPR piping system. The topics covered in this paper are among some of the areas that have evolved form past nuclear power experience
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York, NY (United States)
- ISBN
- 0-7918-0805-X
- Imprint Title
- Codes and standards and applications for design and analysis of pressure vessel and piping components 1991
- Imprint Pagination
- 206 p.
- Journal Page Range
- p. 71-72.
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).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23071389
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BOILERS; DESIGN; ENVIRONMENTAL IMPACTS; FATIGUE; LEAK TESTING; NUCLEAR POWER PLANTS; PERFORMANCE TESTING; PLANNING; PRESSURE VESSELS; PROBABILISTIC ESTIMATION; PRODUCTION REACTORS; REACTOR COMPONENTS; REACTOR SAFETY; REACTOR VESSELS; SAFETY ANALYSIS; SAFETY STANDARDS; US DOE
- Descriptors DEC
- CONTAINERS; MECHANICAL PROPERTIES; NATIONAL ORGANIZATIONS; NUCLEAR FACILITIES; POWER PLANTS; REACTORS; SAFETY; STANDARDS; TESTING; THERMAL POWER PLANTS; US ORGANIZATIONS
Optional Information
- Secondary number(s)
- CONF-910602--.