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Heat Transfer Behaviour and Thermohydraulics Code Testing for Supercritical Water Cooled Reactors (SCWRs)

Abstract

The supercritical water cooled reactor (SCWR) is an innovative water cooled reactor concept which uses water pressurized above its thermodynamic critical pressure as the reactor coolant. This concept offers high thermal efficiencies and a simplified reactor system, and is hence expected to help to improve economic competitiveness. Various kinds of SCWR concepts have been developed, with varying combinations of reactor type (pressure vessel or pressure tube) and core spectrum (thermal, fast or mixed). There is great interest in both developing and developed countries in the research and development (R&D) and conceptual design of SCWRs. Considering the high interest shown in a number of Member States, the IAEA established in 2008 the Coordinated Research Project (CRP) on Heat Transfer Behaviour and Thermo-hydraulics Code Testing for SCWRs. The aim was to foster international collaboration in the R&D of SCWRs in support of Member States’ efforts and under the auspices of the IAEA Nuclear Energy Department’s Technical Working Groups on Advanced Technologies for Light Water Reactors (TWG-LWR) and Heavy Water Reactors (TWG-HWR). The two key objectives of the CRP were to establish accurate databases on the thermohydraulics of supercritical pressure fluids and to test analysis methods for SCWR thermohydraulic behaviour to identify code  More>>
Publication Date:
Aug 15, 2014
Product Type:
Technical Report
Report Number:
IAEA-TECDOC-1746
Resource Relation:
Other Information: Refs., figs., tabs.
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; COOLANTS; COORDINATED RESEARCH PROGRAMS; CRITICAL FLOW; CRITICAL PRESSURE; DEPRESSURIZATION; FLUIDS; HEAVY WATER; IAEA; NATURAL CONVECTION; NUCLEAR ENERGY; TESTING; THERMAL EFFICIENCY; THERMAL HYDRAULICS; WATER COOLED REACTORS; WATER MODERATED REACTORS
OSTI ID:
22264755
Research Organizations:
International Atomic Energy Agency, Nuclear Power Technology Development Section, Vienna (Austria)
Country of Origin:
IAEA
Language:
English
Other Identifying Numbers:
Other: ISBN 978-92-0-107614-4; ISSN 1011-4289; TRN: XA14M5837085985
Availability:
Available from INIS in electronic form. Also available on-line: http://www-pub.iaea.org/MTCD/publications/PDF/TE-1746_web.pdf; Enquiries should be addressed to IAEA, Marketing and Sales Unit, Publishing Section, E-mail: sales.publications@iaea.org; Web site: http://www.iaea.org/books
Submitting Site:
INIS
Size:
510 page(s)
Announcement Date:
Sep 19, 2014

Citation Formats

None. Heat Transfer Behaviour and Thermohydraulics Code Testing for Supercritical Water Cooled Reactors (SCWRs). IAEA: N. p., 2014. Web.
None. Heat Transfer Behaviour and Thermohydraulics Code Testing for Supercritical Water Cooled Reactors (SCWRs). IAEA.
None. 2014. "Heat Transfer Behaviour and Thermohydraulics Code Testing for Supercritical Water Cooled Reactors (SCWRs)." IAEA.
@misc{etde_22264755,
title = {Heat Transfer Behaviour and Thermohydraulics Code Testing for Supercritical Water Cooled Reactors (SCWRs)}
author = {None}
abstractNote = {The supercritical water cooled reactor (SCWR) is an innovative water cooled reactor concept which uses water pressurized above its thermodynamic critical pressure as the reactor coolant. This concept offers high thermal efficiencies and a simplified reactor system, and is hence expected to help to improve economic competitiveness. Various kinds of SCWR concepts have been developed, with varying combinations of reactor type (pressure vessel or pressure tube) and core spectrum (thermal, fast or mixed). There is great interest in both developing and developed countries in the research and development (R&D) and conceptual design of SCWRs. Considering the high interest shown in a number of Member States, the IAEA established in 2008 the Coordinated Research Project (CRP) on Heat Transfer Behaviour and Thermo-hydraulics Code Testing for SCWRs. The aim was to foster international collaboration in the R&D of SCWRs in support of Member States’ efforts and under the auspices of the IAEA Nuclear Energy Department’s Technical Working Groups on Advanced Technologies for Light Water Reactors (TWG-LWR) and Heavy Water Reactors (TWG-HWR). The two key objectives of the CRP were to establish accurate databases on the thermohydraulics of supercritical pressure fluids and to test analysis methods for SCWR thermohydraulic behaviour to identify code development needs. In total, 16 institutes from nine Member States and two international organizations were involved in the CRP. The thermohydraulics phenomena investigated in the CRP included heat transfer and pressure loss characteristics of supercritical pressure fluids, development of new heat transfer prediction methods, critical flow during depressurization from supercritical conditions, flow stability and natural circulation in supercritical pressure systems. Two code testing benchmark exercises were performed for steady state heat transfer and flow stability in a heated channel. The CRP was completed with the planned outputs in 2012. This publication consists of the background and objectives, descriptions of current SCWR design concepts, and major technical achievements from the CRP tasks based on the results of R&D at participating institutes and through their close collaboration. It provides researchers and engineers with a comprehensive and reliable database, and the current status of prediction methods in the area of thermohydraulics of supercritical pressure fluids relevant to SCWRs.}
place = {IAEA}
year = {2014}
month = {Aug}
}