Published February 27, 2007 | Version v1
Report Restricted

Providing the Basis for Innovative Improvements in Advanced LWR Reactor Passive Safety Systems Design: An Educational R and D Project

Description

This project characterizes typical two-phase stratified flow conditions in advanced water reactor horizontal pipe sections, following activation of passive cooling systems. It provides (1) a means to educate nuclear engineering students regarding the importance of two-phase stratified flow in passive cooling systems to the safety of advanced reactor systems and (2) describes the experimental apparatus and process to measure key parameters essential to consider when designing passive emergency core cooling flow paths that may encounter this flow regime. Based on data collected, the state of analysis capabilities can be determined regarding stratified flow in advanced reactor systems and the best paths forward can be identified to ensure that the nuclear industry can properly characterize two-phase stratified flow in passive emergency core cooling systems

Availability note (English)

Available from INIS in electronic form; Also available from OSTI as DE00900897; PURL: https://www.osti.gov/servlets/purl/900897-hs9qIC/

Files

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Additional details

Publishing Information

Imprint Pagination
27 p.
Report number
DOE/ID--14500

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
38105076
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Descriptors DEI
COOLING SYSTEMS; DESIGN; ECCS; NUCLEAR ENGINEERING; NUCLEAR INDUSTRY; SAFETY; WATER
Descriptors DEC
ENERGY SYSTEMS; ENGINEERED SAFETY SYSTEMS; ENGINEERING; HYDROGEN COMPOUNDS; INDUSTRY; OXYGEN COMPOUNDS; REACTOR PROTECTION SYSTEMS

Optional Information

Contract/Grant/Project number
FG07-03ID14500
Notes
doi 10.2172/900897
Funding organization
USDOE - Office of Nuclear Energy, Science and Technology NE (United States)