Published 1976
| Version v1
Book
ASME Code Quality-Assurance Program for nuclear reactors
Creators
Description
To enhance the safety and reliability of vessels, pumps, valves, and piping used in nuclear power systems, the ASME Boiler and Pressure Vessel Code has set forth specific quality-assurance (QA) responsibilities for the owner, the manufacturers, the installers, the ASME, and authorized inspection agencies. In particular, the manufacturers and the installers of such components must operate under a controlled manufacturing system and under detailed QA programs. This approach to controlling the design, fabrication, and installation of nuclear components during the past 3 years has materially improved the integrity of nuclear pressure-boundary and pressure-containing systems
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York
- Imprint Title
- Pressure vessels and piping: design and analysis. IV
- Imprint Pagination
- p. 448-452.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 8315734
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- NUCLEAR POWER PLANTS; PIPES; PLANNING; PRESSURE VESSELS; QUALITY ASSURANCE; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR SAFETY; RELIABILITY; SAFETY ENGINEERING; SPECIFICATIONS
- Descriptors DEC
- CONTAINERS; COOLING SYSTEMS; NUCLEAR FACILITIES; POWER PLANTS; SAFETY; THERMAL POWER PLANTS