Integral and Separate Effects Test Facilities To Support Water Cooled Small Modular Reactors: A Review

Bhowmik, Palash Kumar; Estrada Perez, Carlos Eduardo.; Fishler, Joshua David; Balderrama Prieto, Silvino A.; Reichow, Isaac D.; Johnson, Justin T.; Sabharwall, Piyush; O'Brien, James E.

doi:10.1016/j.pnucene.2023.104697

Title: Integral and Separate Effects Test Facilities To Support Water Cooled Small Modular Reactors: A Review

Journal Article · 02 May 2023 · Progress in Nuclear Energy

DOI: https://doi.org/10.1016/j.pnucene.2023.104697 · OSTI ID:1974620

^[1]; Estrada Perez, Carlos Eduardo. ^[1]; Fishler, Joshua David ^[1]; Balderrama Prieto, Silvino A. ^[1]; Reichow, Isaac D. ^[1]; Johnson, Justin T. ^[1]; Sabharwall, Piyush ^[1]; O'Brien, James E. ^[1]

Idaho National Laboratory (INL), Idaho Falls, ID (United States)

This study reviews previous experimental facilities and test programs relevant to water-cooled reactor system design and analysis to meet regulatory compliances. This study aims to find the best solution for designing the required experiments, obtaining necessary test data, and verifying the developed computer code/models to support the new reactor design and development while minimizing cost and time while leveraging experiences from previous facilities to minimize. Nuclear reactor licensing requires supportive design, analysis, and experimental results to ensure the safety of the full-scale prototype reactor in regular operation, as well as during postulated accident scenarios. These reactor design analyses are generally performed using system codes and other associated simulation tools that require assessment, verification and validation using an appropriate experimental dataset. Experimental facilities used for reactor system safety analysis and system code assessments are categorized into integral effects test (IET) and separate effects test (SET) facilities. Further, these IET and SET experiments and studies use geometrically scaled systems to reproduce the prototype system behavior at a reasonable cost, albeit with some scaling-related distortions. The design challenge of these model facilities is to identify and minimize scaling distortions while reproducing the most important operational phenomena in steady-state operation and in postulated accident scenarios. Lessons learned from previous experimental facilities, models, and correlations can support the development of new multipurpose, scaled, hybrid, integrated, and modular experimental facilities for advanced light water-cooled small modular reactors (SMRs). Successful operation of these facilities can significantly reduce upfront reactor development and demonstration costs and time to deployment.

View Accepted Manuscript (DOE)

Cite

Export

Save

Research Organization:: Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE)

Grant/Contract Number:: DE-AC07-05ID14517; AC07-05ID14517

OSTI ID:: 1974620

Alternate ID(s):: OSTI ID: 1973000

Report Number(s):: INL/JOU-22-70405-Rev001; INL/JOU-22-70405-Rev000; TRN: US2313984

Journal Information:: Progress in Nuclear Energy, Vol. 160, Issue -; ISSN 0149-1970

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

References (38)

Rod bundle thermal-hydraulics experiment with water and water-Al2O3 nanofluid for small modular reactor Bhowmik, Palash K.; Shamim, Jubair A.; Chen, Xiangyi Annals of Nuclear Energy, Vol. 150 https://doi.org/10.1016/j.anucene.2020.107870	journal	January 2021
An investigation of condensation from steam–gas mixtures flowing downward inside a vertical tube Kuhn, S. Z.; Schrock, V. E.; Peterson, P. F. Nuclear Engineering and Design, Vol. 177, Issue 1-3 https://doi.org/10.1016/S0029-5493(97)00185-4	journal	December 1997
An integrated approach to steam condensation studies inside reactor containments: A review Yadav, Mahesh Kumar; Khandekar, Sameer; Sharma, Pavan K. Nuclear Engineering and Design, Vol. 300 https://doi.org/10.1016/j.nucengdes.2016.01.004	journal	April 2016
Review of pool boiling critical heat flux (CHF) and heater rod design for CHF experiments in TREAT Hernandez, Richard; Folsom, Charles P.; Woolstenhulme, Nicolas E. Progress in Nuclear Energy, Vol. 123 https://doi.org/10.1016/j.pnucene.2020.103303	journal	May 2020
Possibilities and Limitations of CFD Simulation for Flashing Flow Scenarios in Nuclear Applications Liao, Yixiang; Lucas, Dirk Energies, Vol. 10, Issue 1 https://doi.org/10.3390/en10010139	journal	January 2017
Review of critical-heat-flux enhancement methods Xie, Shangzhen; Shahmohammadi Beni, Mehrdad; Cai, Jiejin International Journal of Heat and Mass Transfer, Vol. 122 https://doi.org/10.1016/j.ijheatmasstransfer.2018.01.116	journal	July 2018
Evaporation and condensation heat transfer with a noncondensable gas present Murase, M.; Kataoka, Y.; Fujii, T. Nuclear Engineering and Design, Vol. 141, Issue 1-2 https://doi.org/10.1016/0029-5493(93)90098-T	journal	June 1993
MOOSE: Enabling massively parallel multiphysics simulation Permann, Cody J.; Gaston, Derek R.; Andrš, David SoftwareX, Vol. 11 https://doi.org/10.1016/j.softx.2020.100430	journal	January 2020
Modification and application of the system analysis code ATHLET to trans-critical simulations Fu, S. W.; Liu, X. J.; Zhou, C. Annals of Nuclear Energy, Vol. 44 https://doi.org/10.1016/j.anucene.2012.02.005	journal	June 2012
Flow mapping using 3D full-scale CFD simulation and hydrodynamic experiments of an ultra-supercritical turbine’s combined valve for nuclear power plant Bhowmik, Palash K.; Suh, Kune Y. International Journal of Energy and Environmental Engineering, Vol. 12, Issue 3 https://doi.org/10.1007/s40095-021-00394-0	journal	April 2021
Modeling of condensation heat transfer for a PRHRS heat exchanger in a SMART-P plant Lee, Kwon-Yeong; Kim, Moo Hwan Nuclear Engineering and Design, Vol. 238, Issue 12 https://doi.org/10.1016/j.nucengdes.2008.07.005	journal	December 2008
Design and technology development for small modular reactors – Safety expectations, prospects and impediments of their deployment Hidayatullah, H.; Susyadi, S.; Subki, M. Hadid Progress in Nuclear Energy, Vol. 79 https://doi.org/10.1016/j.pnucene.2014.11.010	journal	March 2015
Experiments on Convection Heat Transfer Along a Vertical Flat Plate Between Pools with Different Temperatures Kataoka, Yoshiyuki; Fukui, Tohru; Hatamiya, Shigeo Nuclear Technology, Vol. 99, Issue 3 https://doi.org/10.13182/NT92-A34722	journal	September 1992
Experimental study of two-phase flow structure in large diameter pipes Schlegel, J. P.; Miwa, S.; Chen, S. Experimental Thermal and Fluid Science, Vol. 41 https://doi.org/10.1016/j.expthermflusci.2012.01.034	journal	September 2012
Experimental flow visualization study using particle image velocimetry in a helical coil steam generator with changing lateral pitch geometry Delgado, M.; Hassan, Y. A.; Anand, N. K. International Journal of Heat and Mass Transfer, Vol. 133 https://doi.org/10.1016/j.ijheatmasstransfer.2018.12.152	journal	April 2019
Thermal Hydraulics of Valves for Nuclear Applications Sallet, Dirse W. Nuclear Science and Engineering, Vol. 88, Issue 3 https://doi.org/10.13182/NSE84-A18579	journal	November 1984
Scaling analysis and relation to EMDAP and BEPU Dzodzo, Milorad Nuclear Engineering and Design, Vol. 353 https://doi.org/10.1016/j.nucengdes.2019.110228	journal	November 2019
Forced convection in-tube steam condensation in the presence of noncondensable gases Hasanein, H. A.; Kazimi, M. S.; Golay, M. W. International Journal of Heat and Mass Transfer, Vol. 39, Issue 13 https://doi.org/10.1016/0017-9310(95)00373-8	journal	September 1996
An Experimental Investigation of Flow Boiling Characteristics of Water in Parallel Microchannels Steinke, Mark E.; Kandlikar, Satish G. Journal of Heat Transfer, Vol. 126, Issue 4 https://doi.org/10.1115/1.1778187	journal	May 2004
Validation of the RELAP5 code for the modeling of flashing-induced instabilities under natural-circulation conditions using experimental data from the CIRCUS test facility Kozmenkov, Y.; Rohde, U.; Manera, A. Nuclear Engineering and Design, Vol. 243 https://doi.org/10.1016/j.nucengdes.2011.10.053	journal	February 2012
Development of phenomena identification and ranking table for Westinghouse lead fast reactor's safety Liao, Jun; Ferroni, Paolo; Wright, Richard F. Progress in Nuclear Energy, Vol. 131 https://doi.org/10.1016/j.pnucene.2020.103577	journal	January 2021
The upgraded Cheng and Todreas correlation for pressure drop in hexagonal wire-wrapped rod bundles Chen, S. K.; Chen, Y. M.; Todreas, N. E. Nuclear Engineering and Design, Vol. 335 https://doi.org/10.1016/j.nucengdes.2018.05.010	journal	August 2018
Technology readiness assessment of Small Modular Reactor (SMR) designs Liu, Zhitao; Fan, Jihong Progress in Nuclear Energy, Vol. 70 https://doi.org/10.1016/j.pnucene.2013.07.005	journal	January 2014
The safety goals of the U.S. Nuclear Regulatory Commission Okrent, D. Science, Vol. 236, Issue 4799 https://doi.org/10.1126/science.3563510	journal	April 1987
Steam generator tube rupture (SGTR) scenarios Auvinen, A.; Jokiniemi, J. K.; Lähde, A. Nuclear Engineering and Design, Vol. 235, Issue 2-4 https://doi.org/10.1016/j.nucengdes.2004.08.060	journal	February 2005
Selection of fuel cladding material for nuclear fission reactors Azevedo, C. R. F. Engineering Failure Analysis, Vol. 18, Issue 8 https://doi.org/10.1016/j.engfailanal.2011.06.010	journal	December 2011
Flow boiling heat transfer in a helically coiled steam generator for nuclear power applications Santini, Lorenzo; Cioncolini, Andrea; Butel, Matthew T. International Journal of Heat and Mass Transfer, Vol. 92 https://doi.org/10.1016/j.ijheatmasstransfer.2015.08.012	journal	January 2016
An Experimental Study on the Cooling Characteristics of Passive Containment Cooling Systems Kawakubo, Masahiro; Aritomi, Masanori; Kikura, Hiroshige Journal of Nuclear Science and Technology, Vol. 46, Issue 4 https://doi.org/10.1080/18811248.2007.9711539	journal	April 2009
Surface wettability change during pool boiling of nanofluids and its effect on critical heat flux Kim, S. J.; Bang, I. C.; Buongiorno, J. International Journal of Heat and Mass Transfer, Vol. 50, Issue 19-20 https://doi.org/10.1016/j.ijheatmasstransfer.2007.02.002	journal	September 2007
Small Modular Reactors: Licensing constraints and the way forward Sainati, Tristano; Locatelli, Giorgio; Brookes, Naomi Energy, Vol. 82 https://doi.org/10.1016/j.energy.2014.12.079	journal	March 2015
A state-of-the-art review of recent advances in supercritical natural circulation loops for nuclear applications Sarkar, Milan K. S.; Tilak, Abhilash K.; Basu, Dipankar N. Annals of Nuclear Energy, Vol. 73 https://doi.org/10.1016/j.anucene.2014.06.035	journal	November 2014
Measurement and modeling of two-phase flow parameters in scaled 8×8 BWR rod bundle Yang, X.; Schlegel, J. P.; Liu, Y. International Journal of Heat and Fluid Flow, Vol. 34 https://doi.org/10.1016/j.ijheatfluidflow.2012.02.001	journal	April 2012
State-of-the-art and review of condensation heat transfer for small modular reactor passive safety: Experimental studies Bhowmik, Palash K.; Schlegel, Joshua P.; Revankar, Shripad International Journal of Heat and Mass Transfer, Vol. 192 https://doi.org/10.1016/j.ijheatmasstransfer.2022.122936	journal	August 2022
Research on scaling design and applicability evaluation of integral thermal-hydraulic test facilities: A review Deng, Chengcheng; Zhang, Xueyan; Yang, Ye Annals of Nuclear Energy, Vol. 131 https://doi.org/10.1016/j.anucene.2019.03.042	journal	September 2019
An experimental investigation of a passive cooling unit for nuclear plant containment Liu, H.; Todreas, N. E.; Driscoll, M. J. Nuclear Engineering and Design, Vol. 199, Issue 3 https://doi.org/10.1016/S0029-5493(00)00229-6	journal	July 2000
Application of steam injector to improved safety of light water reactors Takeya, Yuto; Miwa, Shuichiro; Hibiki, Takashi Progress in Nuclear Energy, Vol. 78 https://doi.org/10.1016/j.pnucene.2014.07.045	journal	January 2015
Materials challenges for nuclear systems Allen, Todd; Busby, Jeremy; Meyer, Mitch Materials Today, Vol. 13, Issue 12 https://doi.org/10.1016/S1369-7021(10)70220-0	journal	December 2010
A Condensation Experiment in the Presence of Noncondensables in a Vertical Tube of a Passive Containment Cooling System and Its Assessment with RELAP5/MOD3.2 Park, Hyun Sik; No, Hee Cheon Nuclear Technology, Vol. 127, Issue 2 https://doi.org/10.13182/NT99-A2992	journal	August 1999

Similar Records

Scaling for Nuclear Reactor System: Overview

Conference · 2023 · OSTI ID:2375510

Bhowmik, Palash Kumar

Digitalization, Management and Synthesis of Thermal Hydraulic Legacy Data Using Dynamical System Scaling

Conference · 2022 · OSTI ID:1864286

Reyes, Jose

Investigation of Natural Circulation Instability and Transients in Passively Safe Small Modular Reactors

Technical Report · 2016 · OSTI ID:1346153

Ishii, Mamoru

Related Subjects

42 ENGINEERING
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
small modular reactor
integral effect test
separate effect test
facility development
licensing

Title: Integral and Separate Effects Test Facilities To Support Water Cooled Small Modular Reactors: A Review

Citation Formats

References (38)

Similar Records

Related Subjects