Arthur Rowcliffe
Current Organizations / Institutes
The organizations/institutes from the scholar's latest article
Arthur Rowcliffe has a total of 11 co-authors. Here are the top co-authors by number of shared publications:
A. Hishinuma
Japan Atomic Energy Research Inst., Tokai-Mura (Japan)
1 shared publicationB.A. Chin
Materials Engineering, Auburn University, Auburn, AL 36830, USA
1 shared publicationC.M. Young
Century Tubes Inc., 7910 Dunbrook Road, San Diego, CA 9212, USA
1 shared publication- David. T. Hoelzer
Oak Ridge National Laboratory, Oak Ridge, TN 37831, USA
1 shared publication G.R. Rao
Materials Engineering, Auburn University, Auburn, AL 36830, USA
1 shared publication- Jonathan Edward Menard
Princeton Plasma Physics Laboratory, Princeton, NJ, USA
1 shared publication
Latest Publications
- Open Access
TBM/MTM for HTS-FNSF: An Innovative Testing Strategy to Qualify/Validate Fusion Technologies for U.S. DEMO
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. 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).
Open AccessTBM/MTM for HTS-FNSF: An Innovative Testing Strategy to Qualify/Validate Fusion Technologies for U.S. DEMO
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. 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).
- 1 August 2007
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 367-370, 839-843
Oxidation behavior of a V–4Cr–4Ti alloy during the commercial processing of thin-wall tubing
- 1 August 2007
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 367-370, 839-843
Oxidation behavior of a V–4Cr–4Ti alloy during the commercial processing of thin-wall tubing
- 1 March 1991
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 179-181, 163-164
Radiation effects at fusion reactor He:dpa ratios; overview of U.S./Japan spectral tailoring experiments
- 1 March 1991
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 179-181, 163-164
Radiation effects at fusion reactor He:dpa ratios; overview of U.S./Japan spectral tailoring experiments
- 1 March 1991
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 179-181, 438-440
Development of miniature bending fatigue specimens
- 1 March 1991
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 179-181, 438-440
Development of miniature bending fatigue specimens