Published 1976 | Version v1
Report Restricted

Estimates of the burst reliability of thin-walled cylinders designed to meet the ASME Code allowables

Description

Pressure containment components in nuclear power plants are designed by the conventional deterministic safety factor approach to meet the requirements of the ASME Pressure Vessel Code, Section III. The inevitable variabilities and uncertainties associated with the design, manufacture, installation, and service processes suggest a probabilistic design approach may also be pertinent. Accordingly, the burst reliabilities of two thin-walled 304 SS cylindrical vessels such as might be employed in liquid metal plants are estimated. A large vessel fabricated from rolled plate per ASME SA-240 and a smaller pipe sized vessel also fabricated from rolled plate per ASME SA-358 are considered. The vessels are sized to just meet the allowable ASME Code primary membrance stresses at 8000F (4270C). The bursting probability that the operating pressure is greater than the burst strength of the cylinders is calculated using stress-strength interference theory by direct Monte Carlo simulation on a high speed digital computer. A sensitivity study is employed to identify those design parameters which have the greatest effect on the reliability. The effects of preservice quality assurance defect inspections on the reliability are also evaluated parametrically

Availability note (English)

MF available from INIS under the Report Number.

Files

Restricted

The record is publicly accessible, but files are restricted to users with access.

Additional details

Additional titles

Augmented title (English)
LMFBR

Publishing Information

Imprint Pagination
32 p.
Report number
CONF-760905--11

Conference

Title
International joint pressure vessels and piping and petroleum mechanical engineering conference.
Dates
19 Sep 1976.
Place
Mexico City, Mexico.

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
8284223
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CYLINDERS; FAILURES; LMFBR TYPE REACTORS; PIPES; PROBABILITY; REACTOR COMPONENTS; REACTOR VESSELS; RELIABILITY; RUPTURES
Descriptors DEC
BREEDER REACTORS; CONTAINERS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; REACTORS

Optional Information

Notes
Available from NTIS. $4.00.