Probabilistic Risk Assessment and Radiation Health Physics
Technical Papers Presented
For information on the papers listed, write Communications.
Benke, R.R. and G.R. Adams. 2007. Potential Indoor Worker Exposure from Handling Area Leakage: Example Event Sequence Frequency Analysis. Paper presented at the American Nuclear Society Topical Meeting on Decommissioning, Decontamination, and Reutilization (DD&R 2007), Chattanooga, TN, September.
Nes, R. and R.R. Benke. 2007. Potential Indoor Worker Exposure from Handling Area Leakage: Dose Calculation Methodology and Example Consequence Analysis. Paper presented at the American Nuclear Society Topical Meeting on Decommissioning, Decontamination, and Reutilization (DD&R 2007), Chattanooga, TN, September.
Pensado, O. and J. Mancillas. 2007. Estimates of Mean Consequences and Confidence Bounds on the Mean Associated With Low-Probability Seismic Events in Total System Performance Assessments. 11th International Conference on Environmental Remediation and Radioactive Waste Management; Bruges, Belgium, 2–6 September.
Dasgupta, B., A. Chowdhury, R. Benke, and B. Jagannath. 2003. Review methodology for preclosure safety analysis of proposed geologic repository. Proceedings of the 10th International High-Level Radioactive Waste Management Conference, Las Vegas, Nevada, March 30–April 2, 2003. LaGrange Park, Illinois: American Nuclear Society.
Benke, R., B. Dasgupta, B. Sagar, and A. Chowdhury. 2002. A methodology for preclosure risk assessment for a geologic nuclear waste repository. Proceedings of the 6th International Conference on Probabilistic Safety Assessment and Management, Probabilistic Safety Assessment and Management (PSAM6), San Juan, Puerto Rico, June 23–28, 2002. Oxford, United Kingdom: Elsevier Science, Ltd. Vol. I. pp. 983–988.
Pensado, O., V. Troshanov, B. Sagar, and G. Wittmeyer. 2002. A partitioning method for identifying model parameters. Probabilistic Safety Assessment and Management (PSAM6). E.J. Bonano, A.L. Camp, M.J. Majors, and R.A. Thompson, eds. Kidlington, Oxford, United Kingdom: Elsevier Science, Ltd. Vol. I. pp. 827–833.
Dasgupta, B., D. Daruwalla, R. Benke, A. Chowdhury, and B. Jagannath. 2001. Methodology for assessment of preclosure safety for Yucca Mountain Project. Proceedings of the Ninth International Conference on High-Level Radioactive Waste Management. Las Vegas, Nevada. April 29–May 3, 2001. LaGrange Park, Illinois: American Nuclear Society.
S. Mohanty, T.J. McCartin, R. Codell, R. Rice, R. Janetzke, M. Jarzemba, G. Wittmeyer, G. Cragnolino, S. Stothoff, P. LaPlante, S. Hsiung, G. Rice, T. Ahn, J. Weldy, R. Fedors, C. Mckenney, B. Hill, C. Connor, J. Trapp, R. Abu-Eid, R. Green, B. Leslie, K. Gruss, J.A. Stamatakos, A. Ibrahim, N. Coleman, J. Winterle, A. Ghosh, and W. Murphy. 1999. A total-system performance assessment code for the safety assessment of the proposed high-level nuclear waste repository at Yucca Mountain. EOS Supplement American Geophysical Union. Vol. 80, No. 46. pp. F313–F314.
Mohanty, S., Y. Lu, and J.M. Menchaca. 1999. Preliminary analysis of the Morris Method for identifying influential parameters. American Nuclear Society Transactions. Vol. 81. p. 55.
Smith, M., T.J. McCartin, and S. Mohanty. 1999. TPA 3.2 Code's capability to evaluate the effects of human intrusion. American Nuclear Society Transactions. Vol. 81. p. 53.
Weldy, J.R., R. Codell, M.S. Jarzemba, J.R. Firth, C. Lui, K. Poor, S. Mohanty, and L.M. Deere. 1999. Important input parameters in the U.S. Nuclear Regulatory Commission's Performance Assessment Code for Yucca Mountain. Spring National Meeting of AIChE, March 17–19, Houston, Texas.
McCartin, T., R. Codell, S. Mohanty, R.G. Baca, V. Colten-Bradley, J. Firth, M.R. Byrne, R. Janetzke, and M. Jarzemba. 1998. U.S. NRC's Performance Assessment Capability. Proceedings of the Eighth International Conference on High-Level Radioactive Waste Management, May 11–14, 1998, Las Vegas, Nevada. La Grange Park, Illinois: American Nuclear Society. p. 313.
Mohanty, S., T. McCartin, and R. Codell. 1998. A methodology for probabilistic performance assessment of a high-level nuclear waste repository. Proceedings of the DISTEC '98 International Conference on Radioactive Waste Disposal, Hamburg, Germany, p. 541.
Mohanty, S., G. Cragnolino, D.S. Dunn, N. Sridhar, T. Ahn, R. Codell, and B.J. Davis. 1998. EBSPAC: A computer code for evaluating the performance of the engineered barrier system for HLW disposal. Proceedings of the Eighth International Conference on High-Level Radioactive Waste Management. May 11–14, 1998, Las Vegas, Nevada. La Grange Park, Illinois: American Nuclear Society. p. 411.
Mohanty, S. and G.C. Cragnolino. 1997. Probabilistic assessment of waste package life for high-level radioactive waste disposal. Transactions of the American Nuclear Society. Vol. 76. pp. 48–49.
Prasad, K. and S. Mohanty. 1996. Some observations on real and user introduced uncertainties in conditional simulation. SME Annual Meeting and Exhibit, March 11–14, Phoenix, Arizona, Mining Engineering Journal Supplement. p. 53.
Miklas, M.P., Jr., B. Sagar, A.B. Gureghian, R. Janetzke, H. Karimi, P. LaPlante, S. Mohanty, D. Turner (CNWRA®), and C. Hagg (Swedish Radiation Protection Institute). 1995. SSI toolbox to evaluate Swedish high-level waste disposal system performance. Proceedings of the Sixth Annual International Conference on High-Level Radioactive Waste Management. LaGrange Park, Illinois: American Nuclear Society. pp. 500–502.
Mohanty, S., A.B. Gureghian, B. Sagar (CNWRA®), C. Hagg, and G. Johansson (Swedish Radiation Protection Institute). 1995. A simple model for determining radionuclide release and migration to the biosphere. Proceedings of the Sixth Annual International Conference on High-Level Radioactive Waste Management. LaGrange Park, Illinois: American Nuclear Society. pp. 493–495.
Weiner, R.F., P.A. LaPlante, J.P. Hageman, F. Bennett, J. Buckingham. 1990. Risks in transporting radioactive materials: Comparison of data with NUREG 0170 projections. Proceedings of Waste Management '90, University of Arizona, Tucson, Arizona.
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June 23, 2008