Design of Condensation Heat Transfer Experiment to Evaluate Scaling Distortion in Small Modular Reactor Safety Analysis

Author:

Bhowmik Palash K.1,Schlegel J. P.1,Kalra V.1,Mills C.1,Usman S.1

Affiliation:

1. Department of Nuclear Engineering and Radiation Science, Missouri University of Science and Technology Rolla, Rolla, MO 65401

Abstract

Abstract Designing a novel scaled modular test facility as a part of an experiment for condensation heat transfer (CHT) in small modular reactors (SMRs) is the main focus of this study. This facility will provide data to evaluate models' scalability for predicting heat transfer in the passive containment cooling system (PCCS) of SMR. The nuclear industry recognizes SMRs as future candidates for clean, economic, and safe energy generation. However, licensing requires proper evaluation of the safety systems such as PCCS. The knowledge gap from the literature review showed a lack of high-resolution experimental data for scaling of PCCS and validation of computational fluid dynamics tools. In addition, the presently available test data are inconsistent due to unscaled geometric and varying physics conditions. These inconsistencies lead to inadequate test data benchmarking. To fill this research gap, this study developed three scaled (different diameters) condensing test sections with annular cooling for scale testing and analysis. This facility considered saturated steam as the working fluid with noncondensable gases like nitrogen and helium in different mass fractions. This facility also used a precooler unit for inlet steam conditioning and a postcooler unit for condensate cooling. The high fidelity sensors, instruments, and data acquisition systems are installed and calibrated. Finally, facility safety analysis and shakedown tests are performed.

Publisher

ASME International

Subject

Nuclear Energy and Engineering,Radiation

Reference63 articles.

1. Access to Energy,2020

2. Current Status of Reactors Deployment and Small Modular Reactors Development in the World;ASME J. Nucl. Eng. Radiat. Sci.,2020

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