Demonstration of RELAP5-3D for transient analysis of a dual coolant lead lithium fusion blanket concept

Meehan, Nicholas; Maldonado, G. Ivan; Brown, Nicholas R.

doi:10.1016/j.fusengdes.2022.113192

Demonstration of RELAP5-3D for transient analysis of a dual coolant lead lithium fusion blanket concept

Journal Article · Thu Jun 09 04:00:00 EDT 2022 · Fusion Engineering and Design

DOI:https://doi.org/10.1016/j.fusengdes.2022.113192· OSTI ID:1897709

Meehan, Nicholas ^[1]; Maldonado, G. Ivan ^[2]; ^[2]

Univ. of Tennessee, Knoxville, TN (United States); University of Tennessee, Knoxville
Univ. of Tennessee, Knoxville, TN (United States)

Our research aims to build a multiphysics framework for transient analysis of the Dual- Coolant Lead-Lithium (DCLL) blanket design of the proposed Fusion Nuclear Science Facility (FNSF) for all Onticipated Operational Occurrences (AOOs) using Reduced Order Models (ROMs). This paper presents an assessment of using RELAP5-3D for transient thermal-hydraulic blanket analysis of the DCLL design. Preliminary validation studies for the RELAP5-3D properties were conducted using a representative vertical flow loop model and a comparison study using experimental data from the thermal convection corrosion loops at ORNL. These studies inspected the thermal hydraulic response of Lead-Lithium Eutectic (PbLi) systems within the RELAP5-3D code; mainly pressure drop and heat transfer, as compared to analytical calculations and experimental data. The Magnetohydrodynamic (MHD) pressure drop effect for liquid metal under the effects of a uniform magnetic field was implemented into our models using an equivalent forms loss coefficient based on the phasic momentum equations. We verified our implementation of MHD pressure drop within RELAP5-3D using a systematic approach consisting of two studies. Models were developed to perform comparison studies based on experimental data from the Argonne Liquid metal EXperiment (ALEX) facility and the Magnetohydrodynamic PbLi Experiment (MaPLE) facility. Using the developed validation basis, we built a simplified DCLL channel model within RELAP5-3D, inspected MHD pressure drop and performed transient temperature analysis. The DCLL channel model used radial heating data from the International Thermonuclear Experimental Reactor (ITER) which was normalized to the FNSF design. Here, a representative startup transient was performed using a relative power curve from the initial ramp up of a long-term power pulse of the Tore Supra reactor. This study demonstrated that RELAP5-3D ROMs are capable of accurate transient analysis of the DCLL blanket. We have since utilized MCNP to develop heating profiles based on the FNSF design and are working toward implementing them into our DCLL model.

View Accepted Manuscript (DOE)

Research Organization:: Univ. of Tennessee, Knoxville, TN (United States)

Sponsoring Organization:: USDOE Office of Science (SC), Fusion Energy Sciences (FES)

Grant/Contract Number:: SC0022308

OSTI ID:: 1897709

Journal Information:: Fusion Engineering and Design, Journal Name: Fusion Engineering and Design Vol. 180; ISSN 0920-3796

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

References (53)

The thermal conductivity of AISI 304L stainless steel Graves, R. S.; Kollie, T. G.; McElroy, D. L. International Journal of Thermophysics, Vol. 12, Issue 2 https://doi.org/10.1007/BF00500761	journal	March 1991
Simulations and Experiments to Reach Numerical Multiphase Informations for Security Analysis on Large Volume Vacuum Systems Like Tokamaks Lupelli, I.; Malizia, A.; Richetta, M. Journal of Fusion Energy, Vol. 34, Issue 5 https://doi.org/10.1007/s10894-015-9905-8	journal	March 2015
Transient thermal-hydraulics considerations of tandem mirror LiPb cooled blankets during start-up/shutdown operations Taghavi, Kaveh; Ghoniem, Nasr M. Nuclear Engineering and Design. Fusion, Vol. 1, Issue 4 https://doi.org/10.1016/0167-899X(84)90011-9	journal	January 1984
Primary loop conditioning and design constraints of LiPb cooled tandem mirror reactors during start-up/shutdown operations Taghavi, Kaveh; Ghoniem, Nasr M. Nuclear Engineering and Design. Fusion, Vol. 1, Issue 4 https://doi.org/10.1016/0167-899X(84)90012-0	journal	January 1984
A generic semi-implicit coupling methodology for use in RELAP5-3D© Weaver, W. L.; Tomlinson, E. T.; Aumiller, D. L. Nuclear Engineering and Design, Vol. 211, Issue 1 https://doi.org/10.1016/S0029-5493(01)00422-8	journal	January 2002
Fusion safety codes: international modeling with MELCOR and ATHENA–INTRA Marshall, T.; Porfiri, M. T.; Topilski, L. Fusion Engineering and Design, Vol. 63-64 https://doi.org/10.1016/S0920-3796(02)00249-1	journal	December 2002
Code development for analysis of MHD pressure drop reduction in a liquid metal blanket using insulation technique based on a fully developed flow model Smolentsev, Sergey; Morley, Neil; Abdou, Mohamed Fusion Engineering and Design, Vol. 73, Issue 1 https://doi.org/10.1016/j.fusengdes.2005.01.003	journal	April 2005
Preliminary thermal-hydraulics design of the dual-cooled lithium lead blanket for FDS-II Wang, Hongyan; Wang, Weihua; Bai, Yunqing Fusion Engineering and Design, Vol. 75-79 https://doi.org/10.1016/j.fusengdes.2005.06.252	journal	November 2005
Numerical analysis of MHD flow and heat transfer in a poloidal channel of the DCLL blanket with a SiCf/SiC flow channel insert Smolentsev, S.; Abdou, M.; Morley, N. B. Fusion Engineering and Design, Vol. 81, Issue 1-7 https://doi.org/10.1016/j.fusengdes.2005.07.007	journal	February 2006
Preliminary safety analysis of Korea Helium Cooled Solid Breeder Test Blanket Module Ahn, Mu-Young; Cho, Seungyon; Kim, Duck Hoi Fusion Engineering and Design, Vol. 83, Issue 10-12 https://doi.org/10.1016/j.fusengdes.2008.06.059	journal	December 2008
Numerical analysis of MHD duct flow with a flow channel insert Zhang, Xiujie; Xu, Zengyu; Pan, Chuanjie Fusion Engineering and Design, Vol. 85, Issue 10-12 https://doi.org/10.1016/j.fusengdes.2010.08.007	journal	December 2010
Overview of the ITER TBM Program Giancarli, L. M.; Abdou, M.; Campbell, D. J. Fusion Engineering and Design, Vol. 87, Issue 5-6 https://doi.org/10.1016/j.fusengdes.2011.11.005	journal	August 2012
Construction and initial operation of MHD PbLi facility at UCLA Smolentsev, S.; Li, F. -C.; Morley, N. Fusion Engineering and Design, Vol. 88, Issue 5 https://doi.org/10.1016/j.fusengdes.2013.03.018	journal	June 2013
Experimental and numerical studies of pressure drop in PbLi flows in a circular duct under non-uniform transverse magnetic field Li, F. -C.; Sutevski, D.; Smolentsev, S. Fusion Engineering and Design, Vol. 88, Issue 11 https://doi.org/10.1016/j.fusengdes.2013.08.006	journal	November 2013
An approach to verification and validation of MHD codes for fusion applications Smolentsev, S.; Badia, S.; Bhattacharyay, R. Fusion Engineering and Design, Vol. 100 https://doi.org/10.1016/j.fusengdes.2014.04.049	journal	November 2015
Blanket/first wall challenges and required R&D on the pathway to DEMO Abdou, Mohamed; Morley, Neil B.; Smolentsev, Sergey Fusion Engineering and Design, Vol. 100 https://doi.org/10.1016/j.fusengdes.2015.07.021	journal	November 2015
Methodology for accident analyses of fusion breeder blankets and its application to helium-cooled pebble bed blanket Panayotov, Dobromir; Grief, Andrew; Merrill, Brad J. Fusion Engineering and Design, Vol. 109-111 https://doi.org/10.1016/j.fusengdes.2015.11.019	journal	November 2016
MHD PbLi experiments in MaPLE loop at UCLA Courtessole, C.; Smolentsev, S.; Sketchley, T. Fusion Engineering and Design, Vol. 109-111 https://doi.org/10.1016/j.fusengdes.2016.01.032	journal	November 2016
Numerical modeling of first experiments on PbLi MHD flows in a rectangular duct with foam-based SiC flow channel insert Smolentsev, S.; Courtessole, C.; Abdou, M. Fusion Engineering and Design, Vol. 108 https://doi.org/10.1016/j.fusengdes.2016.04.035	journal	October 2016
Qualification of MELCOR and RELAP5 models for EU HCPB TBS accident analyses Murgatroyd, Julian T.; Owen, Simon; Grief, Andrew Fusion Engineering and Design, Vol. 124 https://doi.org/10.1016/j.fusengdes.2017.02.083	journal	November 2017
Qualification of MELCOR and RELAP5 models for EU HCLL TBS accident analyses Grief, Andrew; Owen, Simon; Murgatroyd, Julian Fusion Engineering and Design, Vol. 124 https://doi.org/10.1016/j.fusengdes.2017.03.048	journal	November 2017
SiC-based sandwich material for Flow Channel Inserts in DCLL blankets: Manufacturing, characterization, corrosion tests Soto, Carlota; García-Rosales, Carmen; Echeberria, Jon Fusion Engineering and Design, Vol. 124 https://doi.org/10.1016/j.fusengdes.2017.05.059	journal	November 2017
Overview of the fusion nuclear science facility, a credible break-in step on the path to fusion energy Kessel, C. E.; Blanchard, J. P.; Davis, A. Fusion Engineering and Design, Vol. 135 https://doi.org/10.1016/j.fusengdes.2017.05.081	journal	October 2018
Neutronics aspects of the FESS-FNSF Davis, A.; Harb, M.; El-Guebaly, L. Fusion Engineering and Design, Vol. 135 https://doi.org/10.1016/j.fusengdes.2017.06.008	journal	October 2018
MHD thermohydraulics analysis and supporting R&D for DCLL blanket in the FNSF Smolentsev, Sergey; Rhodes, Tyler; Pulugundla, Gautam Fusion Engineering and Design, Vol. 135 https://doi.org/10.1016/j.fusengdes.2017.06.017	journal	October 2018
Multiphysics modeling of the FW/Blanket of the U.S. fusion nuclear science facility (FNSF) Huang, Y.; Tillack, M. S.; Ghoniem, N. M. Fusion Engineering and Design, Vol. 135 https://doi.org/10.1016/j.fusengdes.2017.07.005	journal	October 2018
An equation of state for liquid Pb83Li17 Humrickhouse, P. W.; Merrill, B. J. Fusion Engineering and Design, Vol. 127 https://doi.org/10.1016/j.fusengdes.2017.11.023	journal	February 2018
BB LOCA analysis for the reference design of the EU DEMO HCPB blanket concept Jin, Xue Zhou Fusion Engineering and Design, Vol. 136 https://doi.org/10.1016/j.fusengdes.2018.04.046	journal	November 2018
Modelling an in-vessel loss of coolant accident in the EU DEMO WCLL breeding blanket with the GETTHEM code Froio, Antonio; Bertinetti, Andrea; Ciattaglia, Sergio Fusion Engineering and Design, Vol. 136 https://doi.org/10.1016/j.fusengdes.2018.04.106	journal	November 2018
Literature review of lead-lithium thermophysical properties Martelli, D.; Venturini, A.; Utili, M. Fusion Engineering and Design, Vol. 138 https://doi.org/10.1016/j.fusengdes.2018.11.028	journal	January 2019
Mitigation of MHD phenomena in DCLL blankets by Flow Channel Inserts based on a SiC-sandwich material concept Soto, C.; Smolentsev, S.; García-Rosales, C. Fusion Engineering and Design, Vol. 151 https://doi.org/10.1016/j.fusengdes.2019.111381	journal	February 2020
Analysis of the effects of primary heat transfer system isolation valves in case of in-vessel loss-of-coolant accidents in the EU DEMO Froio, A.; Barucca, L.; Ciattaglia, S. Fusion Engineering and Design, Vol. 159 https://doi.org/10.1016/j.fusengdes.2020.111926	journal	October 2020
MHD effects and heat transfer analysis in magneto-thermo-fluid-structure coupled field in DCLL blanket Chen, Long; Li, Mingjian; Ni, Mingjiu International Communications in Heat and Mass Transfer, Vol. 84 https://doi.org/10.1016/j.icheatmasstransfer.2017.04.009	journal	May 2017
Prediction of PbLi fluid flow and temperature field in a thermal convection loop for qualification of fusion materials Jiang, Y.; Smolentsev, S.; Jun, J. International Journal of Heat and Mass Transfer, Vol. 172 https://doi.org/10.1016/j.ijheatmasstransfer.2021.121198	journal	June 2021
Compatibility of an FeCrAl alloy with flowing Pb-Li in a thermal convection loop Pawel, Steven J.; Unocic, Kinga A. Journal of Nuclear Materials, Vol. 492 https://doi.org/10.1016/j.jnucmat.2017.04.048	journal	August 2017
Compatibility of FeCrAlMo with flowing PbLi at 500°-650 °C Jun, Jiheon; Unocic, Kinga A.; Lance, Michael J. Journal of Nuclear Materials, Vol. 528 https://doi.org/10.1016/j.jnucmat.2019.151847	journal	January 2020
Thermomechanical analysis of a Flow Channel Insert based on a SiC-sandwich material concept Soto, Carlota; Martínez-Esnaola, José M.; García-Rosales, Carmen Nuclear Materials and Energy, Vol. 7 https://doi.org/10.1016/j.nme.2016.04.005	journal	May 2016
Heat transfer performance for DCLL blanket with no-wetting insulator walls Huang, Hulin; Yin, Shimou; Zhu, Guiping Theoretical and Applied Mechanics Letters, Vol. 9, Issue 3 https://doi.org/10.1016/j.taml.2019.03.003	journal	May 2019
Overview of steady-state operation on the Tore-Supra tokamak Team, G. Martin for the Tore-Supra Nuclear Fusion, Vol. 43, Issue 9 https://doi.org/10.1088/0029-5515/43/9/304	journal	August 2003
Thermohydraulic responses of a water-cooled tokamak fusion DEMO to loss-of-coolant accidents Nakamura, M.; Tobita, K.; Someya, Y. Nuclear Fusion, Vol. 55, Issue 12 https://doi.org/10.1088/0029-5515/55/12/123008	journal	October 2015
Magnetohydrodynamic and thermal analysis of PbLi flows in poloidal channels with flow channel insert for the EU-DCLL blanket Urgorri, F. R.; Smolentsev, S.; Fernández-Berceruelo, I. Nuclear Fusion, Vol. 58, Issue 10 https://doi.org/10.1088/1741-4326/aad299	journal	July 2018
A Methodology for Accident Analysis of Fusion Breeder Blankets and Its Application to Helium-Cooled Lead–Lithium Blanket Panayotov, Dobromir; Poitevin, Yves; Grief, Andrew IEEE Transactions on Plasma Science, Vol. 44, Issue 10 https://doi.org/10.1109/TPS.2016.2607784	journal	October 2016
Book Reviews Shroyer, Gail School Science and Mathematics, Vol. 93, Issue 2 https://doi.org/10.1111/j.1949-8594.1993.tb12205.x	journal	February 1993
Validation Case Results for 2D and 3D MHD Simulations Ni, Ming-Jiu; Munipalli, Ramakanth; Morley, Neil B. Fusion Science and Technology, Vol. 52, Issue 3 https://doi.org/10.13182/FST07-A1552	journal	October 2007
Development of the Lead Lithium (DCLL) Blanket Concept Malang, S.; Tillack, M.; Wong, C. P. C. Fusion Science and Technology, Vol. 60, Issue 1 https://doi.org/10.13182/FST10-212	journal	July 2011
The Fusion Nuclear Science Facility, the Critical Step in the Pathway to Fusion Energy Kessel, C. E.; Blanchard, J. P.; Davis, A. Fusion Science and Technology, Vol. 68, Issue 2 https://doi.org/10.13182/FST14-953	journal	September 2015
MHD Pressure Drop of NaK Flow in Stainless Steel Pipe Miyazaki, Keiji; Kotake, Shoji; Yamaoka, Nobuo Nuclear Technology - Fusion, Vol. 4, Issue 2P2 https://doi.org/10.13182/FST4-2P2-447	journal	September 1983
Influence of Startup, Shutdown and Staged Power Operation on Tandem Mirror Reactor Design Conn, R. W.; Ghoniem, N. M.; Grotz, S. P. Nuclear Technology - Fusion, Vol. 4, Issue 2P2 https://doi.org/10.13182/FST83-A22930	journal	September 1983
Limits on Transient Power Variations during Startup and Shutdown of Li-Pb Cooled TMR Blankets Ghoniem, N. M.; Taghavi, K.; Blanchard, J. Nuclear Technology - Fusion, Vol. 4, Issue 2P3 https://doi.org/10.13182/FST83-A22953	journal	September 1983
Experimental Facility for Studying MHD Effects in Liquid Metal Cooled Blankets Reed, C. B.; Picologlou, B. F.; Dauzvardis, P. V. Fusion Technology, Vol. 8, Issue 1P2A https://doi.org/10.13182/FST85-A40054	journal	July 1985
Verification and Validation of COMSOL Magnetohydrodynamic Models for Liquid Metal Breeding Blankets Technologies Alberghi, Ciro; Candido, Luigi; Testoni, Raffaella Energies, Vol. 14, Issue 17 https://doi.org/10.3390/en14175413	journal	August 2021
Development of a RELAP5/MOD3.3 Module for MHD Pressure Drop Analysis in Liquid Metals Loops: Verification and Validation Melchiorri, Lorenzo; Narcisi, Vincenzo; Giannetti, Fabio Energies, Vol. 14, Issue 17 https://doi.org/10.3390/en14175538	journal	September 2021
A Review of Dangerous Dust in Fusion Reactors: from Its Creation to Its Resuspension in Case of LOCA and LOVA Malizia, Andrea; Poggi, Luigi; Ciparisse, Jean-François Energies, Vol. 9, Issue 8 https://doi.org/10.3390/en9080578	journal	July 2016

Similar Records

Progress on DCLL Blanket Concept

Journal Article · Sun Sep 01 00:00:00 EDT 2013 · Fusion Science and Technology, 64(3):623-630 · OSTI ID:1111209

MHD thermohydraulics analysis and supporting R&D for DCLL blanket in the FNSF

Journal Article · Fri Jun 16 00:00:00 EDT 2017 · Fusion Engineering and Design · OSTI ID:1610064

A RELAP5-3D Model of the Lobo Lead Loop

Journal Article · Fri Jul 26 00:00:00 EDT 2024 · Nuclear Technology · OSTI ID:2437653

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
DCLL
Multiphysics
Numerical simulations
System analysis
Thermal hydraulics

Demonstration of RELAP5-3D for transient analysis of a dual coolant lead lithium fusion blanket concept

Citation Formats

References (53)

Similar Records

Related Subjects