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Thermohydraulic relationships for advanced water cooled reactors

Abstract

This report was prepared in the context of the IAEA's Co-ordinated Research Project (CRP) on Thermohydraulic Relationships for Advanced Water Cooled Reactors, which was started in 1995 with the overall goal of promoting information exchange and co-operation in establishing a consistent set of thermohydraulic relationships which are appropriate for use in analyzing the performance and safety of advanced water cooled reactors. For advanced water cooled reactors, some key thermohydraulic phenomena are critical heat flux (CHF) and post CHF heat transfer, pressure drop under low flow and low pressure conditions, flow and heat transport by natural circulation, condensation of steam in the presence of non-condensables, thermal stratification and mixing in large pools, gravity driven reflooding, and potential flow instabilities. The objectives of the CRP are (1) to systematically list the requirements for thermohydraulic relationships in support of advanced water cooled reactors during normal and accident conditions, and provide details of their database where possible and (2) to recommend and document a consistent set of thermohydraulic relationships for selected thermohydraulic phenomena such as CHF and post-CHF heat transfer, pressure drop, and passive cooling for advanced water cooled reactors. Chapter 1 provides a brief discussion of the background for this CRP, the CRP  More>>
Authors:
"NONE"
Publication Date:
Apr 01, 2001
Product Type:
Technical Report
Report Number:
IAEA-TECDOC-1203
Reference Number:
EDB-01:058580
Resource Relation:
Other Information: Refs, figs, tabs; PBD: Apr 2001
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; COORDINATED RESEARCH PROGRAMS; CRITICAL HEAT FLUX; FILM BOILING; HEAT TRANSFER; IAEA; PRESSURE DROP; REACTOR OPERATION; REACTOR SAFETY; THERMAL ANALYSIS; WATER COOLED REACTORS
OSTI ID:
20169483
Research Organizations:
International Atomic Energy Agency, Vienna (Austria)
Country of Origin:
IAEA
Language:
English
Other Identifying Numbers:
Other: ISSN 1011-4289; TRN: XA0100970024154
Availability:
Available from INIS in electronic form
Submitting Site:
INIS
Size:
351 pages
Announcement Date:

Citation Formats

Thermohydraulic relationships for advanced water cooled reactors. IAEA: N. p., 2001. Web.
Thermohydraulic relationships for advanced water cooled reactors. IAEA.
2001. "Thermohydraulic relationships for advanced water cooled reactors." IAEA.
@misc{etde_20169483,
title = {Thermohydraulic relationships for advanced water cooled reactors}
abstractNote = {This report was prepared in the context of the IAEA's Co-ordinated Research Project (CRP) on Thermohydraulic Relationships for Advanced Water Cooled Reactors, which was started in 1995 with the overall goal of promoting information exchange and co-operation in establishing a consistent set of thermohydraulic relationships which are appropriate for use in analyzing the performance and safety of advanced water cooled reactors. For advanced water cooled reactors, some key thermohydraulic phenomena are critical heat flux (CHF) and post CHF heat transfer, pressure drop under low flow and low pressure conditions, flow and heat transport by natural circulation, condensation of steam in the presence of non-condensables, thermal stratification and mixing in large pools, gravity driven reflooding, and potential flow instabilities. The objectives of the CRP are (1) to systematically list the requirements for thermohydraulic relationships in support of advanced water cooled reactors during normal and accident conditions, and provide details of their database where possible and (2) to recommend and document a consistent set of thermohydraulic relationships for selected thermohydraulic phenomena such as CHF and post-CHF heat transfer, pressure drop, and passive cooling for advanced water cooled reactors. Chapter 1 provides a brief discussion of the background for this CRP, the CRP objectives and lists the participating institutes. Chapter 2 provides a summary of important and relevant thermohydraulic phenomena for advanced water cooled reactors on the basis of previous work by the international community. Chapter 3 provides details of the database for critical heat flux, and recommends a prediction method which has been established through international co-operation and assessed within this CRP. Chapter 4 provides details of the database for film boiling heat transfer, and presents three methods for predicting film boiling heat transfer coefficients developed by institutes participating in this CRP. Chapter 5 compiles a range of pressure drop correlations, and reviews assessments of these relations and the resulting recommendations. Chapter 6 provides general remarks and conclusions, and comments on future research needs in thermohydraulics of advanced water cooled reactors.}
place = {IAEA}
year = {2001}
month = {Apr}
}