Nuclear Reactor Safety and Risk Analysis

D-5 has a long and distinguished record of nuclear reactor safety analyses that have been performed in support of the Nuclear Regulatory Commission's (NRC's) mission to license commercial nuclear reactors in the US. D-5 has supported the NRC in several main areas in the last several years, including:

• Integrated chemical effects and debris testing in support of safety questions related to plugging of the reactor containment sump strainers that recirculate water in the emergency-core cooling systems in pressurized water reactors.
• Vulnerability analysis of potential threats to commercial reactor sites, including threat assessment, damage/consequence assessment, and mitigation/prevention strategies.
• Thermal-hydraulic assessment and support for reactor licensing applications. This work includes support for the NRC's thermal-hydraulic computer code TRACE. TRACE has its origin in the D-5-developed code TRAC.
• Computational Fluid Dynamics (CFD) support for regulatory applications in the NRC. CFD calculations are rapidly becoming the cutting-edge analysis tools for reactor safety applications.

D-5 supports the safe application of nuclear energy and supports the Laboratory's commitment to ensuring that new nuclear technologies and applications receive the highest level of attention.

Biographies

• Faris Badwan
• Dr. Crystal Dale
• Jack Dallman
• Paul Edelmann
• Dr. Marc Klasky
• Dr. Bruce Letellier
• Patrick McClure
• Kyle Ross

Publications

• Letellier, Bruce C.
• Near-Field Atmospheric Dispersion Around Complex Obstacles Using a 3-D Turbulent Fluid-Flow Model (pdf)
• Near-Field Dispersion of Fission Products in Complex Terrain Using a 3-D Turbulent Fluid-Flow Model (pdf)
• Technical Letter Report, GSI-191 Study: Technical Approach for Risk Assessment of PWR Sump-Screen Blockage (pdf)
• Transport Characteristics of Selected PWR LOCA Generated Debris (pdf)
• Computational Fluid Dynamic Simulations of Insulation-Debris Transport Experiments (pdf)
• Los Alamos Technical Evaluation Report: On-Site Audit of Dresden Nuclear Power Plant Emergency Core Cooling System Strainer Blockage Resolution (pdf)
• Metal Extractions from Heterogeneous Surfaces Using Carbon Dioxide Microemulsions (pdf)
• Debris Transport Characteristics (pdf)
• GSI-191: Separate-Effects Characteristics of Debris Transport in Water (pdf)
• GSI-191: The Impact of Debris-Induced Loss of ECCS Recirculation on PWR Core Damage Frequency (pdf)
• GSI-191: Integrated Debris-Transport Tests in Water Using Simulated Contaminant Floor Geometries (pdf)
• GSI-191 Technical Assessment Detailed Blowdown/Washdown Transport Analysis for Pressurized-Water-Reactor Volunteer Plant (pdf)
• GSI-191: Experimental Studies of Loss-of-Coolant-Accident-Generated Debris Accumulations and Head Loss with Emphasis on the Effects of Calcium Silicate Insulation (pdf)
• Small-Scale Experiments: Effects of Chemical Reactions on Debris-Bed Head Loss (pdf)