B. J. Merrill, P. W. Humrickhouse, and R. L. Moore, "A recent version of MELCOR for fusion safety applications," Fusion Engineering and Design 85 (2010) 1479-1483.
M. Shimada, Y. Hatano, P. Calderoni, T. Oda, Y. Oya, M. Sokolov, K. Zhang, G. Cao, R. D. Kolasinski, and J. P. Sharpe, “First result of deuterium retention in neutron-irradiated tungsten exposed to high flux plasma in TPE,” Journal of Nuclear Materials 415 (2011) S667-S671.
M. Shimada, G. Cao, Y. Hatano, T. Oda, Y. Oya, M. Hara, and P. Calderoni, ”Deuterium Depth Profile in Neutron-Irradiated Tungsten Exposed to Plasma,” Physica Scripta T145 (2011) 014051.
B. J. Merrill, P. W. Humrickhouse, and J. P. Sharpe, "An aerosol resuspension model for MELCOR for fusion," Fusion Engineering and Design 86 (2011) 2686-2689.
M. Shimada, Y. Hatano, Y. Oya, T. Oda, M. Hara, G. Cao, M. Kobayashi, M. Sokolov, H. Watanabe, B. Tyburska-Puschel, Y. Ueda, P. Calderoni, and K. Okuno, “Overview of the US-Japan collaborative investigation on hydrogen isotope retention in neutron-irradiated and ion-damaged tungsten,” Fusion Engineering and Design 87 (2012) 1166-1170.
P. W. Humrickhouse and B. J. Merrill, "MELCOR Accident Analysis for ARIES-ACT," Fusion Science and Technology 64 (2013) 340-344.
L. C. Cadwallader and T. Pinna, "Reliability Estimation for Double Containment Piping," Fusion Science and Technology 64 (2013) 351-356.
P. W. Humrickhouse and B. J. Merrill, “ARIES-ACT1 Safety Design and Analysis,” Fusion Science and Technology, 67 (January 2015) 158-166.
P. W. Humrickhouse and B. J. Merrill, “Vacuum Permeator Analysis for Extraction of Tritium from DCLL Blankets,” Fusion Science and Technology, 68 (Sept 2015) 295-302.
P. W. Humrickhouse and B. J. Merrill, “ARIES-ACT1 Safety Design and Analysis,” Fusion Science and Technology, 67 (January 2015) 158-166.
P. W. Humrickhouse and B. J. Merrill, “Vacuum Permeator Analysis for Extraction of Tritium from DCLL Blankets,” Fusion Science and Technology, 68 (Sept 2015) 295-302.
M. Shimada, M. Hara, T. Otsuka, Y. Oya, and Y. Hatano, "Defect annealing and thermal desorption of deuterium in low dose HFIR neutron-irradiated tungsten", Journal of Nuclear Materials, 463 (August 2015) 1005-1008.
M. Shimada, G. Cao, T. Otsuka, M. Hara, M. Kobayashi, Y. Oya and Y. Hatano, “Irradiation effect on deuterium behaviour in low-dose HFIR neutron-irradiated tungsten”, Nuclear Fusion, 55 (2015) 013008.
C. N. Taylor, M. Shimada, B. J. Merrill, D. W. Akers, Y. Hatano, “Development of positron annihilation spectroscopy for investigating deuterium decorated voids in neutron-irradiated tungsten,” Journal of Nuclear Materials, 463 (August 2015) 1009-1012.
B. J. Merrill, “Modeling an unmitigated thermal quench event in a large field magnet in a DEMO reactor,” Fusion Engineering and Design, 98-99 (October 2015) 2196-2200.
L. C. Cadwallader and R. S. Willms, “TSTA piping and flame arrestor operating experience data,” Fusion Engineering and Design, 98-99 (October 2015) 2112-2115.
M. Shimada, M. Hara, T. Otsuka, Y. Oya, and Y. Hatano, "Defect annealing and thermal desorption of deuterium in low dose HFIR neutron-irradiated tungsten", Journal of Nuclear Materials, 463 (August 2015) 1005-1008.
M. Shimada, G. Cao, T. Otsuka, M. Hara, M. Kobayashi, Y. Oya and Y. Hatano, “Irradiation effect on deuterium behaviour in low-dose HFIR neutron-irradiated tungsten”, Nuclear Fusion, 55 (2015) 013008.
C. N. Taylor, M. Shimada, B. J. Merrill, D. W. Akers, Y. Hatano, “Development of positron annihilation spectroscopy for investigating deuterium decorated voids in neutron-irradiated tungsten,” Journal of Nuclear Materials, 463 (August 2015) 1009-1012.
B. J. Merrill, “Modeling an unmitigated thermal quench event in a large field magnet in a DEMO reactor,” Fusion Engineering and Design, 98-99 (October 2015) 2196-2200.
L. C. Cadwallader and R. S. Willms, “TSTA piping and flame arrestor operating experience data,” Fusion Engineering and Design, 98-99 (October 2015) 2112-2115.
