• 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.

Significant publications from the INL Fusion Safety Program
​

• D. A. Petti and K. A. McCarthy, “Progress in US fusion safety and environmental activities over the last decade,” Fusion Technology 37 (2000) 1-23.
• B. J. Merrill, R. L. Moore, S. T. Polkinghorne, “Modifications to the MELCOR code for application in fusion accident analyses,” Fusion Engineering and Design 51-52 (2000) 555-563.
• D. A. Petti, B. Merrill, R. Moore, G. Longhurst, L. El-Guebaly, E. Mogahed, D. Henderson, P. Wilson, A. Abdou, “Safety and
• environmental assessment of ARIES-AT,” Fusion Technology 39 (2001) 449-457.
• G. R. Smolik, R. Pawelko, R. Anderl, D. Petti, “Oxidation and volatilization from tungsten brush high heat flux armor during steam exposure,” Fusion Engineering and Design 54 (2001) 583-591.
• B. J. Merrill, “A lithium-air reaction model for the MELCOR code for analyzing lithium fires in fusion reactors,” Fusion Engineering and Design 54 (2001) 485-493.
• D. A. Petti, R. Anderl, G. Smolik, D.-K. Sze, T. Terai, S. Tanaka, “JUPITER-II Flibe tritium chemistry and safety experimental program,” Fusion Science and Technology 41 (2002) 635-641.
• J. P. Sharpe, D. Petti, H.-W. Bartels, “A review of dust in fusion devices: implications for safety and operational performance,” Fusion Engineering and Design 63-64 (2002) 153-163.
• B. J. Merrill, D.-K. Sze, H. Y. Khater, E. Mogahed, “Safety implications of CLiFF liquid metal first walls,” Fusion Engineering and Design 63-64 (2002) 285-293.
• T. D. Marshall, M. T. Porfiri, L. Topilski, B. J. Merrill, “Fusion safety codes: international modeling with MELCOR and ATHENA-INTRA,” Fusion Engineering and Design 63-64 (2002) 243-249.
• L. Cadwallader and P. Petersen, “Confinement reliability estimates for vacuum system components,” Fusion Science and Technology 44 (2003) 382-387.
• L. C. Cadwallader, “Chemical hazards and safety issues in fusion safety design,” Fusion Science and Technology 44 (2003) 369-374.
• L. C. Cadwallader and D. A. Petti, “Safety in the design of three burning plasma experiments,” Fusion Science and Technology 44 (2003) 388-392.
• G. R. Smolik, R. J. Pawelko, Y. Morimoto, K. Okuno, R. A. Anderl, D. A. Petti, T. Terai, “Mobilization measurements from Flibe under argon and air flow,” Journal of Nuclear Materials 329 (2004) 1322-1326.
• B. J. Merrill, M. Sawan, C. P. C. Wong, R. Nygren, L. Cadwallader, S. Malang, D.-K. Sze, “Safety assessment of two advanced ferritic steel molten salt blanket design concepts,” Fusion Engineering and Design 72 (2004) 277-306.
• R. Anderl, S. Fukada, G. Smolik, R. Pawelko, S. Schuetz, P. Sharpe, B. Merrill, D. Petti, H. Nishimura, T. Terai, S. Tanaka, “Deuterium/tritium behavior in Flibe and Flibe-facing materials,” Journal of Nuclear Materials 329 (2004) 1327-1331.
• L. C. Cadwallader, “Comparison of tritium component failure rate data,” Fusion Science and Technology 47 (2005) 983-988.
• J. P. Sharpe, P. Humrickhouse, C. Skinner, T. Tanabe, K. Masaki, N. Miya, A. Sagara, “Characterization of dust collected from NSTX and JT-60U,” Journal of Nuclear Materials 337 (2005) 1000-1004.
• D. Petti, G. Smolik, M. Simpson, P. Sharpe, R. Anderl, S. Fukada, Y. Hatano, M. Hara, Y. Oya, T. Terai, D.-K. Sze, S. Tanaka, “JUPITER-II molten salt Flibe research: An update on tritium, mobilization and redox chemistry experiments,” Fusion Engineering and Design 81 (2006) 1439-1449.
• D. Petti, B. Merrill, R. Moore, G. Longhurst, L. El-Guebaly, E. Mogahed, D. Henderson, P. Wilson, A. Abdou, “ARIES-AT safety design and analysis,” Fusion Engineering and Design 80 (2006) 111-137.
• B. Merrill, L. El-Guebaly, C. Martin, R. Moore, A. R. Raffray, D. Petti, “Safety assessment of the ARIES compact stellarator design,” Fusion Science and Technology 54 (2008) 838-863.
• P. Calderoni, P. Sharpe, M. Hara, Y. Oya, “Measurement of tritium permeation in flibe (2LiF-BeF2),” Fusion Engineering and Design 83 (2008) 1331-1334.
• P. Sharpe, R. Kolasinski, M. Shimada, P. Calderoni, R. Causey, “Retention behavior in tungsten and molybdenum exposed to high fluences of deuterium ions in TPE,” Journal of Nuclear Materials 390-391 (2009) 709-712.