Published 1994 | Version v1
Book

Leak before break piping evaluation diagram

  • 1. ABB Combustion Engineering Nuclear Power, Windsor, CT (United States)

Description

Traditionally Leak Before Break (LBB) has been applied to the evaluation of piping in existing nuclear plants. This paper presents a simple method for evaluating piping systems for LBB during the design process. This method produces a piping evaluation diagram (PED) which defines the LBB requirements to the piping designer for use during the design process. Several sets of LBB analyses are performed for each different pipe size and material considered in the LBB application. The results of this method are independent of the actual pipe routing. Two complete LBB evaluations are performed to determine the maximum allowable stability load, one evaluation for a low normal operating load, and the other evaluation for a high normal operating load. These normal operating loads span the typical loads for the particular system being evaluated. In developing the allowable loads, the appropriate LBB margins are included in the PED preparation. The resulting LBB solutions are plotted as a set of allowable curves for the maximum design basis load, such is the seismic load versus the normal operating load. Since the required margins are already accounted for in the LBB PED, the piping designer can use the diagram directly with the results of the piping analysis and determine immediately if the current piping arrangement passes LBB. Since the LBB PED is independent of pipe routing, changes to the piping system can be evaluated using the existing PED. For a particular application, all that remains is to confirm that the actual materials and pipe sizes assumed in creating the particular design are built into the plant

Additional details

Publishing Information

Publisher
American Society of Mechanical Engineers.
Imprint Place
New York, NY (United States)
ISBN
0-7918-1356-8
Imprint Title
Plant systems/components aging management 1994. PVP-Vol. 283
Imprint Pagination
122 p.
Journal Page Range
p. 111-115.

Conference

Title
1994 pressure vessels and piping conference.
Dates
19-23 Jun 1994.
Place
Minneapolis, MN (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
26021569
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
DESIGN; EVALUATION; FAILURES; NUCLEAR POWER PLANTS; PIPES; SEISMIC EFFECTS; STANDARDS
Descriptors DEC
NUCLEAR FACILITIES; POWER PLANTS; THERMAL POWER PLANTS

Optional Information

Secondary number(s)
CONF-940613--.