Published 1992
| Version v1
Book
ASME pressure vessel code application to nuclear waste container design
Creators
- 1. Dept. of Mechanical Engineering, Univ. of Nevada, Las Vegas, NV (United States)
Description
It would be highly desirable if a widely accepted standard could be applied t the design of permanent nuclear waste storage containers, to ensure their integrity. One such standard is the ASME Pressure Vessel Code. In this paper, the authors explore the applicability of this code to the design process of spent nuclear fuel storage containers. The authors identify a list of the major sections of the code that are related to the waste container design. These sections have been investigated and then applied to a preliminary spent fuel container design. A comparison of the six candidate materials performance is presented
Additional details
Publishing Information
- Publisher
- American Nuclear Society.
- Imprint Place
- La Grange Park, IL (United States)
- ISBN
- 0-87262-891-4
- Imprint Title
- Proceedings of high level radioactive waste management
- Imprint Pagination
- 2425 p.
- Journal Page Range
- p. 1244-1252.
Conference
- Title
- 3. international high level radioactive waste management (IHLRWM) conference.
- Dates
- 12-16 Apr 1992.
- Place
- Las Vegas, NV (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24012276
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S42: ENGINEERING; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CODES; CONTAINERS; DESIGN; MATERIALS TESTING; PERFORMANCE TESTING; PRESSURE VESSELS; RADIOACTIVE WASTE STORAGE; SPENT FUEL STORAGE
- Descriptors DEC
- MANAGEMENT; STORAGE; TESTING; WASTE MANAGEMENT; WASTE STORAGE
Optional Information
- Secondary number(s)
- CONF-920430--.