Evaluations of core melt frequency effects due to component aging and maintenance WE Vesely, RE Kurth, SM Scalzo US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Div …, 1990 | 52 | 1990 |
Experimental study of countercurrent steam condensation A Segev, LJ Flanigan, RE Kurth, RP Collier | 51 | 1981 |
Development of computational framework and architecture for extremely low probability of rupture (xLPR) code D Rudland, P Mattie, R Kurth, H Klasky, B Bishop, D Harris Pressure Vessels and Piping Conference 49255, 629-640, 2010 | 24 | 2010 |
Discrete probability distributions for probabilistic fracture mechanics RE Kurth, DC Cox Risk Analysis 5 (3), 235-240, 1985 | 24 | 1985 |
Development of the PRO-LOCA probabilistic fracture mechanics code P Scott, R Kurth, A Cox, R Olson, D Rudland Swedish Radiation Safety Authority (SSM), Stockholm, Sweden MERIT Final …, 2010 | 16 | 2010 |
Development of non-idealized surface to through-wall crack transition model DJ Shim, R Kurth, D Rudland Pressure Vessels and Piping Conference 55706, V06AT06A089, 2013 | 12 | 2013 |
A process for risk-focused maintenance EV Lofgren, SE Cooper, RE Kurth, LB Phillips Nuclear Regulatory Commission, Washington, DC (USA). Div. of Regulatory …, 1991 | 12 | 1991 |
Benchmarking probabilistic code for LBB analysis for circumferential cracks RE Kurth, CJ Sallaberry, BA Young, P Scott, FW Brust, E Kurth Pressure Vessels and Piping Conference 57915, V01BT01A003, 2017 | 9 | 2017 |
Weld Residual Stress Inputs for a Probabilistic Fracture Mechanics Code ML Benson, FW Brust, RE Kurth, JE Broussard Pressure Vessels and Piping Conference 46049, V06BT06A050, 2014 | 9 | 2014 |
Development of the PRO-LOCA Probabilistic Fracture Mechanics Code, MERIT Final Report P Scott, R Kurth, A Cox, R Olson, D Rudland | 9 | 2010 |
Composite load spectra for select space propulsion structural components JF Newell, HW Ho, RE Kurth | 8 | 1991 |
Importance ranking based on aging considerations of components included in probabilistic risk assessments T Davis, A Shafaghi, R Kurth, F Leverenz Battelle Columbus Labs., OH (USA), 1985 | 8 | 1985 |
Continuing Development of PRO-LOCA for the Prediction of Break Probabilities for Loss-Of-Coolant Accidents D Rudland, P Scott, R Kurth, A Cox ASME Pressure Vessels and Piping Conference 43697, 1827-1836, 2009 | 7 | 2009 |
Statistical analysis of ECC bypass data using a nonlinear constrained maximum likelihood estimation technique TA Bishop, RP Collier, RE Kurth Nuclear Engineering and Design 64 (1), 87-91, 1981 | 7 | 1981 |
Probabilistic risk analysis applied to the space-shuttle main engine JR Fragola, R Kurth, G Maggio, SA Epstein, MV Frank Proceedings of Annual Reliability and Maintainability Symposium (RAMS), 494-503, 1994 | 6 | 1994 |
Comparison of Different Thermal Aging Models to Assess Fully Aged Toughness in Cast Austenitic Stainless Steels MF Uddin, GM Wilkowski, RE Kurth, FW Brust, DJ Shim, D Rudland Pressure Vessels and Piping Conference 56932, V01BT01A012, 2015 | 5 | 2015 |
Benchmarking xLPR version 1.0 with the PRO-LOCA version 3.0 Code R Kurth, E Kurth, B Young, A Cox, R Olson, P Scott, D Rudland, R Iyengar, ... Pressure Vessels and Piping Conference 55058, 723-729, 2012 | 5 | 2012 |
Probabilistic Approach for Fatigue Life Assessment Based on SN Curve Z Wei, RE Kurth, TP Forte Pressure Vessels and Piping Conference 49224, 677-685, 2010 | 5 | 2010 |
Overview of the MERIT (Maximizing Enhancements in Risk Informed Technology) Program P Scott, B Brust, R Kurth, D Rudland, G Wilkowski IASMiRT, 2007 | 5 | 2007 |
Uncertainty analysis of light water reactor meltdown accident consequences: Methodology development P Baybutt, RE Kurth Battelle Columbus Laboratories, 1978 | 5 | 1978 |