Understanding and Prediction of Thermal Hydraulics Phenomena Relevant to Supercritical Water Cooled Reactors

Closed for proposals

Project Type

Coordinated Research Project

Project Code

I31025

CRP

2000

Approved Date

5 September 2013

Status

3 - Active - Ongoing

Start Date

19 June 2014

Expected End Date

19 June 2019

Participating Countries

Canada
China
Germany
Hungary
India
Italy
Russian Federation
Ukraine
United Kingdom of Great Britain and Northern Ireland
United States of America

Description

The supercritical water cooled reactor (SCWR) is one of the innovative water cooled reactor (WCR) concepts mainly for large scale production of electricity. By utilizing its high coolant temperature, the SCWR is expected to achieve much higher thermal efficiencies than those of current WCRs, and thereby promise improved economics. The objective of the CRP is to improve the understanding and prediction accuracy of thermal hydraulics phenomena relevant to SCWRs and to benchmark numerical toolsets for their analysis. Several key phenomena, such as heat transfer, pressure drop and flow stability, have been identified as crucial to the successful development of SCWRs. This CRP will enhance understanding of thermal hydraulics phenomena, sharing of experimental and analytical results, prediction methods for key thermal hydraulics parameters, and cross-training of personnel between participating institutes.

Objectives

The overall objective of the CRP is to improve the understanding of thermal-hydraulics phenomena and prediction accuracy of thermal-hydraulics parameters related to SCWRs and to benchmark numerical toolsets for SCWR thermal-hydraulics analyses.

Specific objectives

1) Improve predictive capability of heat transfer for SCWR fuel related geometries.

2) Improve predictive capability of pressure drop for SCWR fuel related geometries.

3) Improve predictive capability of natural circulation and parallel channel stability boundary.

4) Improve predictive capability of critical flow.

5) Improve predictive capability of CHF at near critical pressures.

6) Improve predictive capability of subchannel flow.

Improve predictive capability of critical flow.

Improve predictive capability of Critical Heat Flux (CHF) at near critical pressures.

Improve predictive capability of heat transfer for SCWR fuel related geometries including separate effects.

Improve predictive capability of natural circulation flow.

Improve predictive capability of parallel channel stability boundary.

Improve predictive capability of pressure drop for SCWR fuel related geometries including separate effects.

Improve predictive capability of sub-channel and plenum mixing.

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