Published 1993
| Version v1
Book
Analysis of liquid slug motion in a voided line
Creators
- 1. Wuhan Univ. of Hydraulic and Electric Engineering, Hubei (China). Dept. of Hydroelectric Engineering
- 2. Michigan State Univ., East Lansing, MI (United States). Dept. of Civil and Environmental Engineering
Description
This paper describes an analysis of the pressure transient resulting from a pump locked rotor event in the primary system of a pressurized water reactor (PWR). The objective of this study is to define the loads on primary system components during the transient. It is found that, although this pressure transient is less severe than those which are typical of design basis pipe breaks, it could be a significant transient for plants which have been exempted from the larger pipe breaks
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York, NY (United States)
- ISBN
- 0-7918-0980-3
- Imprint Title
- Fluid-structure interaction, transient thermal-hydraulics, and structural mechanics
- Imprint Pagination
- 211 p.
- Journal Page Range
- p. 123-130.
Conference
- Title
- 1993 pressure vessel and piping conference.
- Dates
- 25-29 Jul 1993.
- Place
- Denver, CO (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 25025963
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- B CODES; COMPUTER CODES; DESIGN; FLUID-STRUCTURE INTERACTIONS; LOSS OF COOLANT; PIPES; PRIMARY COOLANT CIRCUITS; PUMPS; PWR TYPE REACTORS; ROTORS; RUPTURES; TRANSIENTS; WATER HAMMER
- Descriptors DEC
- ACCIDENTS; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; EQUIPMENT; FAILURES; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-930702--Vol.253.