Publications

Middleton, B.D., Rodriguez, S.B., Carlson, M., & Carlson, M. (2015). Design Construction and Operation of a Supercritical Carbon Dioxide (sCO₂) Loop for Investigation of Dry Cooling and Natural Circulation Potential for Use in Advanced Small Modular Reactors Utilizing sCO₂ Power Conversion Cycles. 10.2172/1226786

Middleton, B.D. (2015). Advanced SMRs Using S-CO2 Power Conversion with Dry Cooling. 10.2172/1490532

Middleton, B.D., Carlson, M., & Carlson, M. (2015). Sandia National Laboratories' Air-Cooled Natural Circulation Loop for Supercritical Carbon Dioxide [Conference Poster]. https://www.osti.gov/biblio/1324240

Middleton, B.D., Boland, T.R., Schlafli, W.E., Landrey, B., & Landrey, B. (2015). Assessment of Small Modular Reactor Suitability for Use on or Near Air Force Space Command Installations. 10.2172/1490530

Middleton, B.D. (2013). Integrating Safety, Operations, Security, and Safeguards (ISOSS) into the design of small modular reactors : a handbook. 10.2172/1121986

Middleton, B.D., Wheeler, T.A., Farnum, C.O., Duran, F.A., Jordan, S.E., Baum, G., & Baum, G. (2013). Evaluation of the applicability of existing nuclear power plant regulatory requirements in the U.S. to advanced small modular reactors. 10.2172/1095926

Cipiti, B.B., Duran, F.A., Middleton, B.D., Key, R., & Key, R. (2011). Fully integrated safeguards and security for reprocessing plant monitoring. https://doi.org/10.2172/1029760

Houf, W.G., Middleton, B.D., & Middleton, B.D. (2009). Analyses to support development of risk-informed separation distances for hydrogen codes and standards. 10.2172/983689

Middleton, B.D. (2008). A hierarchical Bayesian approach to passive system reliability analysis [Conference]. American Nuclear Society - International Topical Meeting on Probabilistic Safety Assessment and Analysis, PSA 2008. https://www.scopus.com/inward/record.uri?partnerID=HzOxMe3b&scp=70449939010&origin=inward

Middleton, B.D. (2008). Joint Modeling of Degradation and Failure Rate Occurrence Using Bayesian Networks [Conference]. https://www.osti.gov/biblio/1142401

Brown, J., Middleton, B.D., Robinson, D.G., & Robinson, D.G. (2008). Data for the Use in Quantitative Risk Analysis of Hydrogen Refueling Stations [Conference]. https://www.osti.gov/biblio/1145869

Middleton, B.D. (2008). NUCLEAR HYDROGEN AND CAPTURED CARBON DIOXIDE FOR ALTERNATIVE LIQUID FUELS. Nuclear Technology. https://www.osti.gov/biblio/1145909

Middleton, B.D., Kazimi, M.S., & Kazimi, M.S. (2007). Nuclear hydrogen and captured carbon dioxide for alternative liquid fuels [Conference]. American Nuclear Society Embedded Topical Meeting - 2007 International Topical Meeting on Safety and Technology of Nuclear Hydrogen Production, Control, and Management. https://www.scopus.com/inward/record.uri?partnerID=HzOxMe3b&scp=36448989780&origin=inward

Middleton, B.D. (2007). Joint Modeling of Degradation and Failure Rate Occurrence Using Bayesian Networks [Presentation]. https://www.osti.gov/biblio/1716624

Middleton, B.D. (2007). Facilitating the Construction of Nuclear Power Plants in the U.S [Presentation]. https://www.osti.gov/biblio/1716613

Middleton, B.D. (2007). Overview of Approach for Launch Safety Analysis for Nuclear Power Systems at Sandia National Laboratories [Presentation]. https://www.osti.gov/biblio/1724346