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Past Publications

​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.