TBM/MTM for HTS-FNSF: An Innovative Testing Strategy to Qualify/Validate Fusion Technologies for U.S. DEMO
Abstract
The qualification and validation of nuclear technologies are daunting tasks for fusion demonstration (DEMO) and power plants. This is particularly true for advanced designs that involve harsh radiation environment with 14 MeV neutrons and high-temperature operating regimes. This paper outlines the unique qualification and validation processes developed in the U.S., offering the only access to the complete fusion environment, focusing on the most prominent U.S. blanket concept (the dual cooled PbLi (DCLL)) along with testing new generations of structural and functional materials in dedicated test modules. The venue for such activities is the proposed Fusion Nuclear Science Facility (FNSF), which is viewed as an essential element of the U.S. fusion roadmap. A staged blanket testing strategy has been developed to test and enhance the DCLL blanket performance during each phase of FNSF D-T operation. A materials testing module (MTM) is critically important to include in the FNSF as well to test a broad range of specimens of future, more advanced generations of materials in a relevant fusion environment. Here, the most important attributes for MTM are the relevant He/dpa ratio (10–15) and the much larger specimen volumes compared to the 10–500 mL range available in the International Fusion Materials Irradiationmore »
- Authors:
- Publication Date:
- Research Org.:
- Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)
- Sponsoring Org.:
- USDOE
- OSTI Identifier:
- 1426824
- Alternate Identifier(s):
- OSTI ID: 1329251
- Grant/Contract Number:
- US DOE Contract #DE-AC02-09CH11466; AC02-09CH11466
- Resource Type:
- Published Article
- Journal Name:
- Energies
- Additional Journal Information:
- Journal Name: Energies Journal Volume: 9 Journal Issue: 8; Journal ID: ISSN 1996-1073
- Publisher:
- MDPI AG
- Country of Publication:
- Switzerland
- Language:
- English
- Subject:
- 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; testing strategy; testing blanket module; materials testing module; fusion nuclear testing facility; spherical tokamak; high temperature superconducting magnets
Citation Formats
El-Guebaly, Laila, Rowcliffe, Arthur, Menard, Jonathan, and Brown, Thomas. TBM/MTM for HTS-FNSF: An Innovative Testing Strategy to Qualify/Validate Fusion Technologies for U.S. DEMO. Switzerland: N. p., 2016.
Web. doi:10.3390/en9080632.
El-Guebaly, Laila, Rowcliffe, Arthur, Menard, Jonathan, & Brown, Thomas. TBM/MTM for HTS-FNSF: An Innovative Testing Strategy to Qualify/Validate Fusion Technologies for U.S. DEMO. Switzerland. https://doi.org/10.3390/en9080632
El-Guebaly, Laila, Rowcliffe, Arthur, Menard, Jonathan, and Brown, Thomas. Thu .
"TBM/MTM for HTS-FNSF: An Innovative Testing Strategy to Qualify/Validate Fusion Technologies for U.S. DEMO". Switzerland. https://doi.org/10.3390/en9080632.
@article{osti_1426824,
title = {TBM/MTM for HTS-FNSF: An Innovative Testing Strategy to Qualify/Validate Fusion Technologies for U.S. DEMO},
author = {El-Guebaly, Laila and Rowcliffe, Arthur and Menard, Jonathan and Brown, Thomas},
abstractNote = {The qualification and validation of nuclear technologies are daunting tasks for fusion demonstration (DEMO) and power plants. This is particularly true for advanced designs that involve harsh radiation environment with 14 MeV neutrons and high-temperature operating regimes. This paper outlines the unique qualification and validation processes developed in the U.S., offering the only access to the complete fusion environment, focusing on the most prominent U.S. blanket concept (the dual cooled PbLi (DCLL)) along with testing new generations of structural and functional materials in dedicated test modules. The venue for such activities is the proposed Fusion Nuclear Science Facility (FNSF), which is viewed as an essential element of the U.S. fusion roadmap. A staged blanket testing strategy has been developed to test and enhance the DCLL blanket performance during each phase of FNSF D-T operation. A materials testing module (MTM) is critically important to include in the FNSF as well to test a broad range of specimens of future, more advanced generations of materials in a relevant fusion environment. Here, the most important attributes for MTM are the relevant He/dpa ratio (10–15) and the much larger specimen volumes compared to the 10–500 mL range available in the International Fusion Materials Irradiation Facility (IFMIF) and European DEMO-Oriented Neutron Source (DONES).},
doi = {10.3390/en9080632},
journal = {Energies},
number = 8,
volume = 9,
place = {Switzerland},
year = {Thu Aug 11 00:00:00 EDT 2016},
month = {Thu Aug 11 00:00:00 EDT 2016}
}
https://doi.org/10.3390/en9080632
Web of Science
Works referenced in this record:
Fusion nuclear science facilities and pilot plants based on the spherical tokamak
journal, August 2016
- Menard, J. E.; Brown, T.; El-Guebaly, L.
- Nuclear Fusion, Vol. 56, Issue 10
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
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
Overview of EU DEMO design and R&D activities
journal, October 2014
- Federici, G.; Kemp, R.; Ward, D.
- Fusion Engineering and Design, Vol. 89, Issue 7-8
Recent Developments in Irradiation-Resistant Steels
journal, August 2008
- Odette, G. R.; Alinger, M. J.; Wirth, B. D.
- Annual Review of Materials Research, Vol. 38, Issue 1, p. 471-503
Prospects for pilot plants based on the tokamak, spherical tokamak and stellarator
journal, August 2011
- Menard, J. E.; Bromberg, L.; Brown, T.
- Nuclear Fusion, Vol. 51, Issue 10
Options and methods for instrumentation of Test Blanket Systems for experiment control and scientific mission
journal, October 2014
- Calderoni, Pattrick; Ricapito, Italo; Zmitko, Milan
- Fusion Engineering and Design, Vol. 89, Issue 7-8
Tritium breeder blankets design and technologies in Europe: Development status of ITER Test Blanket Modules, test & qualification strategy and roadmap towards DEMO
journal, December 2010
- Poitevin, Y.; Boccaccini, L. V.; Zmitko, M.
- Fusion Engineering and Design, Vol. 85, Issue 10-12
Development of ODS FeCrAl for Compatibility in Fusion and Fission Energy Applications
journal, November 2014
- Pint, B. A.; Dryepondt, S.; Unocic, K. A.
- JOM, Vol. 66, Issue 12
Progresses and challenges in supporting activities toward a license to operate European TBM systems in ITER
journal, October 2014
- Poitevin, Y.; Ricapito, I.; Zmitko, M.
- Fusion Engineering and Design, Vol. 89, Issue 7-8
The accomplishment of the Engineering Design Activities of IFMIF/EVEDA: The European–Japanese project towards a Li(d,xn) fusion relevant neutron source
journal, July 2015
- Knaster, J.; Ibarra, A.; Abal, J.
- Nuclear Fusion, Vol. 55, Issue 8
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
Impurity effects on reduced-activation ferritic steels developed for fusion applications
journal, August 2000
- Klueh, R. L.; Cheng, E. T.; Grossbeck, M. L.
- Journal of Nuclear Materials, Vol. 280, Issue 3
Materials R&D for a timely DEMO: Key findings and recommendations of the EU Roadmap Materials Assessment Group
journal, October 2014
- Stork, Derek; Agostini, Pietro; Boutard, Jean-Louis
- Fusion Engineering and Design, Vol. 89, Issue 7-8
Development of Sandwich Flow Channel Inserts for an EU DEMO Dual Coolant Blanket Concept
journal, October 2015
- Norajitra, Prachai; Basuki, Widodo Widjaja; Gonzalez, Maria
- Fusion Science and Technology, Vol. 68, Issue 3
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
Overview of the ITER TBM Program
journal, August 2012
- Giancarli, L. M.; Abdou, M.; Campbell, D. J.
- Fusion Engineering and Design, Vol. 87, Issue 5-6
Nuclear Aspects and Blanket Testing/Development Strategy for ST-FNSF
journal, May 2014
- El-Guebaly, Laila; Mynsberge, Lucas; Menard, Jonathan
- IEEE Transactions on Plasma Science, Vol. 42, Issue 5
Advanced power core system for the ARIES-AT power plant
journal, February 2007
- Raffray, A. R.; El-Guebaly, L.; Malang, S.
- Fusion Engineering and Design, Vol. 82, Issue 2
Current design of the European TBM systems and implications on DEMO breeding blanket
journal, November 2016
- Ricapito, ; Calderoni, P.; Aiello, A.
- Fusion Engineering and Design, Vol. 109-111
Objectives and status of EUROfusion DEMO blanket studies
journal, November 2016
- Boccaccini, L. V.; Aiello, G.; Aubert, J.
- Fusion Engineering and Design, Vol. 109-111
A Stepped Approach from IFMIF/EVEDA Toward IFMIF
journal, August 2014
- Ibarra, A.; Heidinger, R.; Barabaschi, P.
- Fusion Science and Technology, Vol. 66, Issue 1
Multimodal options for materials research to advance the basis for fusion energy in the ITER era
journal, September 2013
- Zinkle, S. J.; Möslang, A.; Muroga, T.
- Nuclear Fusion, Vol. 53, Issue 10
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
Development of the Helium Cooled Lithium Lead blanket for DEMO
journal, October 2014
- Aiello, G.; Aubert, J.; Jonquères, N.
- Fusion Engineering and Design, Vol. 89, Issue 7-8
An overview of the US DCLL ITER-TBM program
journal, December 2010
- Wong, C. P. C.; Abdou, M.; Dagher, M.
- Fusion Engineering and Design, Vol. 85, Issue 7-9
A preliminary conceptual design study for Korean fusion DEMO reactor
journal, October 2013
- Kim, Keeman; Kim, Hyoung Chan; Oh, Sangjun
- Fusion Engineering and Design, Vol. 88, Issue 6-8