Published 1992 | Version v1
Book

ASME pressure vessel code application to nuclear waste container design

  • 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--.