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Title: A review of thermal hydraulics systems analysis for breeding blanket design and future needs for fusion engineering demonstration facility design and licensing

Authors:
; ; ; ORCiD logo; ORCiD logo; ; ORCiD logo; ORCiD logo
Publication Date:
Sponsoring Org.:
USDOE Office of Science (SC), Fusion Energy Sciences (FES)
OSTI Identifier:
1808325
Grant/Contract Number:  
AC05-00OR22725
Resource Type:
Publisher's Accepted Manuscript
Journal Name:
Fusion Engineering and Design
Additional Journal Information:
Journal Name: Fusion Engineering and Design Journal Volume: 172 Journal Issue: C; Journal ID: ISSN 0920-3796
Publisher:
Elsevier
Country of Publication:
Netherlands
Language:
English

Citation Formats

Seo, Seok Bin, Hernandez, Richard, O'Neal, Miles, Meehan, Nicholas, Novais, Felipe S., Rizk, Marina, Maldonado, G. Ivan, and Brown, Nicholas R. A review of thermal hydraulics systems analysis for breeding blanket design and future needs for fusion engineering demonstration facility design and licensing. Netherlands: N. p., 2021. Web. doi:10.1016/j.fusengdes.2021.112769.
Seo, Seok Bin, Hernandez, Richard, O'Neal, Miles, Meehan, Nicholas, Novais, Felipe S., Rizk, Marina, Maldonado, G. Ivan, & Brown, Nicholas R. A review of thermal hydraulics systems analysis for breeding blanket design and future needs for fusion engineering demonstration facility design and licensing. Netherlands. https://doi.org/10.1016/j.fusengdes.2021.112769
Seo, Seok Bin, Hernandez, Richard, O'Neal, Miles, Meehan, Nicholas, Novais, Felipe S., Rizk, Marina, Maldonado, G. Ivan, and Brown, Nicholas R. Mon . "A review of thermal hydraulics systems analysis for breeding blanket design and future needs for fusion engineering demonstration facility design and licensing". Netherlands. https://doi.org/10.1016/j.fusengdes.2021.112769.
@article{osti_1808325,
title = {A review of thermal hydraulics systems analysis for breeding blanket design and future needs for fusion engineering demonstration facility design and licensing},
author = {Seo, Seok Bin and Hernandez, Richard and O'Neal, Miles and Meehan, Nicholas and Novais, Felipe S. and Rizk, Marina and Maldonado, G. Ivan and Brown, Nicholas R.},
abstractNote = {},
doi = {10.1016/j.fusengdes.2021.112769},
journal = {Fusion Engineering and Design},
number = C,
volume = 172,
place = {Netherlands},
year = {Mon Nov 01 00:00:00 EDT 2021},
month = {Mon Nov 01 00:00:00 EDT 2021}
}

Works referenced in this record:

Development of a model for the thermal-hydraulic characterization of the He-FUS3 loop
journal, October 2015


Effect of ELM pacing on morphology evolution and erosion of tungsten as a plasma-facing material in a fusion environment
journal, September 2018


LOCA, LOFA and LOVA analyses pertaining to NET/ITER safety design guidance
journal, December 1991


Modifications to the MELCOR-TMAP code to simultaneously treat multiple fusion coolants
journal, September 2019


European development of He-cooled divertors for fusion power plants
journal, October 2005


Initial Nuclear Assessment for a Low Aspect Ratio Power Plant
journal, December 1996


Facilities, testing program and modeling needs for studying liquid metal magnetohydrodynamic flows in fusion blankets
journal, November 2015


An integrated model of tritium transport and corrosion in Fluoride Salt-Cooled High-Temperature Reactors (FHRs) – Part I: Theory and benchmarking
journal, December 2016


LOFA Analysis for US ITER Solid Breeder Blanket
journal, May 1991

  • Ying, A. Y.; Raffray, A. R.; Abdou, M. A.
  • Fusion Technology, Vol. 19, Issue 3P2B
  • DOI: 10.13182/FST91-A29550

Magnetohydrodynamic and Thermal Issues of the SiC f /SiC Flow Channel Insert
journal, July 2006

  • Smolentsev, S.; Morley, N. B.; Abdou, M.
  • Fusion Science and Technology, Vol. 50, Issue 1
  • DOI: 10.13182/FST06-A1226

Acoustic Properties of Pb-17Li Alloy for Ultrasonic Doppler Velocimetry
journal, August 2009

  • Ueki, Y.; Hirabayashi, M.; Kunugi, T.
  • Fusion Science and Technology, Vol. 56, Issue 2
  • DOI: 10.13182/FST56-846

Steady-state operation in compact tokamaks with copper coils
journal, May 2011


Modeling and simulation functional needs for molten salt reactor licensing
journal, December 2019


Overview of the fusion nuclear science facility, a credible break-in step on the path to fusion energy
journal, October 2018


Analysis of Turbulent Heat Transfer in Rectangular Flow Channels inside the First Wall of Blanket Modules
journal, December 2014


Application of regression, variance, and density based global sensitivity methods to integrated VERA-CS and BISON simulations
journal, June 2018


First principles review of options for tritium breeder and neutron multiplier materials for breeding blankets in fusion reactors
journal, December 2018


Thermal-hydraulic system study of a high pressure, high temperature helium loop using RELAP5-3D code
journal, August 2012


Self-cooled blanket concepts using Pb7Li as liquid breeder and coolant
journal, April 1991


The EU advanced dual coolant blanket concept
journal, November 2002


Application of the Denovo Discrete Ordinates Radiation Transport Code to Large-Scale Fusion Neutronics
journal, August 2018


Multiphysics modeling of the FW/Blanket of the U.S. fusion nuclear science facility (FNSF)
journal, October 2018


Transient pressure propagation behavior in PbLi loop system triggered by in-box LOCA accident of DFLL blanket
journal, May 2019


Lessons learnt from ITER safety & licensing for DEMO and future nuclear fusion facilities
journal, October 2014


Review of recent MHD activities for liquid metal blankets in the US
journal, January 2017

  • Smolentsev, S.; Abdou, M.; Courtessole, C.
  • Magnetohydrodynamics, Vol. 53, Issue 2
  • DOI: 10.22364/mhd.53.2.21

Development of the Lead Lithium (DCLL) Blanket Concept
journal, July 2011

  • Malang, S.; Tillack, M.; Wong, C. P. C.
  • Fusion Science and Technology, Vol. 60, Issue 1
  • DOI: 10.13182/FST10-212

Status of the engineering activities carried out on the European DCLL
journal, November 2017


Numerical modeling of first experiments on PbLi MHD flows in a rectangular duct with foam-based SiC flow channel insert
journal, October 2016


Thermal-hydraulic modeling and analyses of the water-cooled EU DEMO using RELAP5 system code
journal, September 2019


Tritium permeation experiment using a tungsten armored divertor-simulating module
journal, December 2000


Vacuum Permeator Analysis for Extraction of Tritium from DCLL Blankets
journal, September 2015

  • Humrickhouse, Paul W.; Merrill, Brad J.
  • Fusion Science and Technology, Vol. 68, Issue 2
  • DOI: 10.13182/FST14-941

Physics Basis of a Fusion Development Facility Utilizing the Tokamak Approach
journal, January 2010

  • Chan, V. S.; Stambaugh, R. D.; Garofalo, A. M.
  • Fusion Science and Technology, Vol. 57, Issue 1
  • DOI: 10.13182/FST10-A9269

Thermal diffusion of tritium in Nb metal
journal, January 1981


Fusion Nuclear Science Facility (FNSF) before Upgrade to Component Test Facility (CTF)
journal, August 2011

  • Peng, Y. K. M.; Canik, J. M.; Diem, S. J.
  • Fusion Science and Technology, Vol. 60, Issue 2
  • DOI: 10.13182/FST60-441

Corrosion behavior of EUROFER steel in flowing eutectic Pb–17Li alloy
journal, August 2004


Temperature dependence of for protium, deuterium and tritium in niobium
journal, May 1985


Hydrogen permeation in FeCrAl alloys for LWR cladding application
journal, June 2015


Progress in the ITER Physics Basis
journal, June 2007


Preliminary accident analysis of Loss of Off-Site Power and In-Box LOCA for the CFETR helium cooled solid breeder blanket
journal, May 2017


Conceptual design of a component test facility based on the spherical tokamak
journal, December 2008


Overview of the HCPB Research Activities in EUROfusion
journal, June 2018

  • Hernandez, Francisco A.; Arbeiter, Frederik; Boccaccini, Lorenzo V.
  • IEEE Transactions on Plasma Science, Vol. 46, Issue 6
  • DOI: 10.1109/TPS.2018.2830813

Development of a helium-cooled divertor: Material choice and technological studies
journal, August 2007


Compatibility behavior of EUROFER steel in flowing Pb–17Li
journal, April 2009


Design of a permeator against vacuum for tritium extraction from eutectic lithium-lead in a DCLL DEMO
journal, April 2017


Challenges for plasma-facing components in nuclear fusion
journal, September 2019

  • Linke, Jochen; Du, Juan; Loewenhoff, Thorsten
  • Matter and Radiation at Extremes, Vol. 4, Issue 5
  • DOI: 10.1063/1.5090100

Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: Core design and safety analysis
journal, May 2017


Study of EU DEMO WCLL breeding blanket and primary heat transfer system integration
journal, November 2018


Toward the ultimate goal of tritium self-sufficiency: Technical issues and requirements imposed on ARIES advanced power plants
journal, December 2009


An overview of dual coolant Pb–17Li breeder first wall and blanket concept development for the US ITER-TBM design
journal, February 2006


Investigation of heat transfer in a steam generator bayonet tube for the development of PbLi technology for EU DEMO fusion reactor
journal, October 2020


ELM mitigation techniques
journal, July 2013


Effect of ELMS and disruptions on FNSF plasma-facing components
journal, October 2018


Prediction and mitigation of disruptions in ASDEX Upgrade
journal, March 2001


Thermal Diffusion of Tritium and Protium in Alpha Phase of Zirconium
journal, September 1988


Plasma facing and high heat flux materials – needs for ITER and beyond
journal, December 2002


Effects of ELMs and disruptions on ITER divertor armour materials
journal, March 2005


State-of-the-Art 3-D Assessment of Elements Degrading TBR of ARIES-ACT SiC/LiPb Blanket
journal, September 2013

  • El-Guebaly, L.; Jaber, A.; Mynsberge, L.
  • Fusion Science and Technology, Vol. 64, Issue 3
  • DOI: 10.13182/FST13-A19155

Qualification of MELCOR and RELAP5 models for EU HCPB TBS accident analyses
journal, November 2017


An overview of the US DCLL ITER-TBM program
journal, December 2010


Status of the EU DEMO HCLL breeding blanket design development
journal, November 2018


The McCad Code for the Automatic Generation of MCNP 3-D Models: Applications in Fusion Neutronics
journal, March 2014

  • Moro, Fabio; Fischer, Ulrich; Lu, Lei
  • IEEE Transactions on Plasma Science, Vol. 42, Issue 4, p. 1036-1041
  • DOI: 10.1109/TPS.2014.2308957

A recent version of MELCOR for fusion safety applications
journal, December 2010


ITER TBM Program and associated system engineering
journal, November 2018


A Methodology for Accident Analysis of Fusion Breeder Blankets and Its Application to Helium-Cooled Lead–Lithium Blanket
journal, October 2016

  • Panayotov, Dobromir; Poitevin, Yves; Grief, Andrew
  • IEEE Transactions on Plasma Science, Vol. 44, Issue 10
  • DOI: 10.1109/TPS.2016.2607784

Experimental campaign on pressure wave propagation in LLE
journal, November 2018


The Impacts of Liquid Metal Plasma-Facing Components on Fusion Reactor Safety and Tritium Management
journal, November 2019


Experimental evaluation of tritium permeation through stainless steel tubes of heat exchanger from primary to secondary water in ITER
journal, August 2004


Fuzzy-neural approaches to the prediction of disruptions in ASDEX Upgrade
journal, November 2001


Hydrogen Isotope Retention and Permeation in Neutron-Irradiated Tungsten and Tungsten Alloys Under PHENIX Collaboration
journal, August 2017


Tritium Transport in Poloidal Flows of a DCLL Blanket
journal, August 2011

  • Pattison, M. J.; Smolentsev, S.; Munipalli, R.
  • Fusion Science and Technology, Vol. 60, Issue 2
  • DOI: 10.13182/FST10-309

Tritium Transport Issues for Helium-Cooled Breeding Blankets
journal, July 2014

  • Franza, Fabrizio; Boccaccini, Lorenzo Virgillio; Demange, David
  • IEEE Transactions on Plasma Science, Vol. 42, Issue 7
  • DOI: 10.1109/TPS.2014.2329573

ITER, safety and licensing
journal, October 2007


THALLIUM: An experimental facility for simulation of HCLL In-box LOCA and validation of RELAP5-3D system code
journal, November 2017


Analyses of loss of vacuum accident (LOVA) in ITER
journal, January 2000


ITER Neutronics Modeling Using Hybrid Monte Carlo/Deterministic and CAD-Based Monte Carlo Methods
journal, July 2011

  • Ibrahim, Ahmad M.; Mosher, Scott W.; Evans, Thomas M.
  • Nuclear Technology, Vol. 175, Issue 1
  • DOI: 10.13182/NT175-251

Review of MARFE phenomena in tokamaks
journal, February 1987


Variance-based sensitivity analysis applied to hydrogen migration and redistribution model in Bison. Part I: Simulation of historical experiments
journal, October 2019


Qualification of MELCOR and RELAP5 models for EU HCLL TBS accident analyses
journal, November 2017


Experimental study of liquid metal magnetohydrodynamic flows near gaps between flow channel inserts
journal, September 2019


Status of Pb-16Li technologies for European DEMO fusion reactor
journal, September 2019


Neutronic assessments towards a comprehensive design of DEMO with DCLL breeding blanket
journal, January 2019


Remote Handling and Plasma Conditions to Enable Fusion Nuclear Science R&D Using a Component Testing Facility
journal, August 2009

  • Peng, Y. K. M.; Burgess, T. W.; Carroll, A. J.
  • Fusion Science and Technology, Vol. 56, Issue 2
  • DOI: 10.13182/FST09-A9034

Preliminary safety analysis of ex-vessel LOCA for the European HCPB TBM system
journal, August 2012


Fusion–Fission Transmutation Scheme—Efficient destruction of nuclear waste
journal, January 2009


MHD effects and heat transfer analysis in magneto-thermo-fluid-structure coupled field in DCLL blanket
journal, May 2017


Thermal Hydraulic Safety Assessment of LLCB Test Blanket System in ITER Using Modified relap/scdapsim/mod4.0 Code
journal, March 2018

  • Saraswat, S. P.; Munsh, P.; Khanna, A.
  • Journal of Nuclear Engineering and Radiation Science, Vol. 4, Issue 2
  • DOI: 10.1115/1.4038823

MHD thermohydraulics analysis and supporting R&D for DCLL blanket in the FNSF
journal, October 2018


Progress in the physics basis of a Fusion Nuclear Science Facility based on the Advanced Tokamak concept
journal, May 2014


Multidimensional simulations of hydrides during fuel rod lifecycle
journal, November 2015


The physics and technology basis entering European system code studies for DEMO
journal, October 2016


Experimental and RELAP5-3D results on IELLLO (Integrated European Lead Lithium LOop) operation
journal, November 2017


The Fusion Nuclear Science Facility, the Critical Step in the Pathway to Fusion Energy
journal, September 2015

  • Kessel, C. E.; Blanchard, J. P.; Davis, A.
  • Fusion Science and Technology, Vol. 68, Issue 2
  • DOI: 10.13182/FST14-953

A component test facility based on the spherical tokamak
journal, November 2005


Acceleration techniques for the direct use of CAD-based geometry in fusion neutronics analysis
journal, December 2010


Development of a helium-cooled divertor concept: design-related requirements on materials and fabrication technology
journal, August 2004


DC electrical conductivity of silicon carbide ceramics and composites for flow channel insert applications
journal, April 2009


Overview of recent ITER TBM Program activities
journal, September 2020


Double-Layer Flow Channel Insert for Electric and Thermal Insulation in the Dual-Coolant Lead-Lithium Blanket
journal, July 2009

  • Smolentsev, Sergey; Malang, Siegfried
  • Fusion Science and Technology, Vol. 56, Issue 1
  • DOI: 10.13182/FST09-A8902

The use of water in a fusion power core
journal, February 2015


Accident analysis with MELCOR-fusion code for DONES lithium loop and accelerator
journal, September 2019


Continuous SiC fiber, CVI SiC matrix composites for nuclear applications: Properties and irradiation effects
journal, May 2014


Overview of the ARIES-RS reversed-shear tokamak power plant study
journal, December 1997

  • Najmabadi, Farrokh; Bathke, Charles G.; Billone, Michael C.
  • Fusion Engineering and Design, Vol. 38, Issue 1-2
  • DOI: 10.1016/S0920-3796(97)00110-5

An overview of the EU breeding blanket design strategy as an integral part of the DEMO design effort
journal, April 2019


Overview of ARIES-RS neutronics and radiation shielding: key issues and main conclusions
journal, December 1997


Thermohydraulic responses of a water-cooled tokamak fusion DEMO to loss-of-coolant accidents
journal, October 2015


Thermal-Hydraulic and Neutronic Phenomena Important in Modeling and Simulation of Liquid-Fuel Molten Salt Reactors
journal, April 2019


Code-to-Code Comparison for a PbLi Mixed-Convection MHD Flow
journal, July 2020


Mission and Readiness Assessment for Fusion Nuclear Facilities
journal, September 2013

  • Neilson, G. H.; Neilson, G. H.; Brown, T. G.
  • Fusion Science and Technology, Vol. 64, Issue 3
  • DOI: 10.13182/FST13-A19137

Assessment of neutron irradiation effects on RAFM steels
journal, March 2013


Thermomechanical Analysis of the Revised U.S. ITER DCLL Test Blanket Module
journal, July 2011

  • Aoyama, Aaron T.; Sharafat, Shahram; Ghoniem, Nasr
  • Fusion Science and Technology, Vol. 60, Issue 1
  • DOI: 10.13182/FST11-A12347

Neutronics aspects of the FESS-FNSF
journal, October 2018


Neutronics Characteristics and Shielding System for ARIES-ACT1 Power Plant
journal, January 2015

  • EL-Guebaly, L.; Mynsberge, L.; Team, Aries-Act
  • Fusion Science and Technology, Vol. 67, Issue 1
  • DOI: 10.13182/FST14-791

Recent US activities on advanced He-cooled W-alloy divertor concepts for fusion power plants
journal, January 2011


Tritium aspects of the fusion nuclear science facility
journal, October 2018


Key Aspects of the Safety Study of a Water-Cooled Fusion DEMO Reactor
journal, January 2014

  • Nakamura, Makoto; Tobita, Kenji; Someya, Youji
  • Plasma and Fusion Research, Vol. 9, Issue 0
  • DOI: 10.1585/pfr.9.1405139

Fusion nuclear science facilities and pilot plants based on the spherical tokamak
journal, August 2016


Development Status of a SiC-Foam Based Flow Channel Insert for a U.S.-ITER DCLL TBM
journal, August 2009

  • Sharafat, Shahram; Aoyama, Aaron; Morley, Neil
  • Fusion Science and Technology, Vol. 56, Issue 2
  • DOI: 10.13182/FST09-7

RELAP5-3D Code Includes ATHENA Features and Models
conference, September 2008

  • Riemke, Richard A.; Davis, Cliff B.; Schultz, Richard R.
  • 14th International Conference on Nuclear Engineering, Volume 2: Thermal Hydraulics
  • DOI: 10.1115/ICONE14-89217

Impact of Pressure Equalization Slot in Flow Channel Insert on Tritium Transport in a DCLL-Type Poloidal Duct
journal, September 2013

  • Zhang, H.; Ying, A.; Abdou, M.
  • Fusion Science and Technology, Vol. 64, Issue 3
  • DOI: 10.13182/FST12-579

Modeling and simulation of hydrogen behavior in Zircaloy-4 fuel cladding
journal, September 2014


Construction and initial operation of MHD PbLi facility at UCLA
journal, June 2013


Methodology for accident analyses of fusion breeder blankets and its application to helium-cooled pebble bed blanket
journal, November 2016


Tritium transport experiments on the JET tokamak
journal, November 2004


Magnetohydrodynamic and thermal analysis of PbLi flows in poloidal channels with flow channel insert for the EU-DCLL blanket
journal, July 2018

  • Urgorri, F. R.; Smolentsev, S.; Fernández-Berceruelo, I.
  • Nuclear Fusion, Vol. 58, Issue 10
  • DOI: 10.1088/1741-4326/aad299

Verification of Modelica-Based Models with Analytical Solutions for Tritium Diffusion
journal, March 2018


Design and Evaluation of Nuclear System for ARIES-ACT2 Power Plant with DCLL Blanket
journal, May 2017


ITER safety and licensing update
journal, August 2012


Optimization process for the design of the DCLL blanket for the European DEMOnstration fusion reactor according to its nuclear performances
journal, May 2017

  • Palermo, Iole; Rapisarda, David; Fernández-Berceruelo, Iván
  • Nuclear Fusion, Vol. 57, Issue 7
  • DOI: 10.1088/1741-4326/aa6c14

Lead–lithium eutectic material database for nuclear fusion technology
journal, June 2008


The European Breeding Blanket Test Facility: An integrated device to test European helium cooled TBMs in view of ITER
journal, June 2009


Thermal-hydraulic design of a DCLL breeding blanket for the EU DEMO
journal, November 2017


A review of ELMs in divertor tokamaks
journal, February 1997


Sensitivity analysis of VERA-CS and FRAPCON coupling in a multiphysics environment
journal, January 2018


Experimental and numerical studies of pressure drop in PbLi flows in a circular duct under non-uniform transverse magnetic field
journal, November 2013


Fusion Nuclear Science Facility Candidates
journal, February 2011

  • Stambaugh, R. D.; Chan, V. S.; Garofalo, A. M.
  • Fusion Science and Technology, Vol. 59, Issue 2
  • DOI: 10.13182/FST59-279

Blanket system selection for the ARIES-ST
journal, September 2000


The Future of Low-Carbon Electricity
journal, October 2017


Comparison of global sensitivity analysis methods – Application to fuel behavior modeling
journal, February 2016


Thermal–hydraulic and safety analysis for Chinese helium-cooled solid breeder TBM cooling system
journal, January 2013


Blanket/first wall challenges and required R&D on the pathway to DEMO
journal, November 2015


Disruption mitigation on Alcator C-Mod using high-pressure gas injection: Experiments and modeling toward ITER
journal, June 2007


Dual-coolant lead–lithium (DCLL) blanket status and R&D needs
journal, November 2015


Critical safety issues in the design of fusion machines
journal, April 1991


Vertical displacement events: A serious concern in future ITER operation
journal, December 2008


Status and Future of the Tritium Plasma Experiment
journal, October 1995

  • Causey, Rion A.; Buchenauer, Dean; Taylor, Dave
  • Fusion Technology, Vol. 28, Issue 3P2
  • DOI: 10.13182/FST95-A30561

Uncertainty quantification and sensitivity analysis with CASL Core Simulator VERA-CS
journal, September 2016


Three-Dimensional Neutronics Study for ARIES-ST Power Plant
journal, November 1998


Application of ADVANTG to the JET3 – NEXP streaming benchmark experiment
journal, October 2019


Experimental campaign on the upgraded He-FUS3 facility
journal, November 2017


Sensitivity analysis of fusion power plant designs using the SYCOMORE system code
journal, November 2019