Lawrence Livermore National Laboratory



The Quantitative Risk Analysis group utilizes computational methods to analyze a variety of risks associated with the design and operation of radiological, nuclear, and chemical facilities. Our expertise includes Monte Carlo simulations of radiation transport, safety compliance for packaging and transportation of radioactive materials, nuclear safeguards technology development, system engineering and statistical analysis for nuclear material management, gamma spectroscopic analysis, hazard and accident analyses, safety basis documentation, quantification of margin and uncertainty, and sensitivity analysis.


Hesham Khater, 925-422-2620
Group Leader



ContactPhoneDiscipline Expertise
Brian Anderson 925-422-2685 Radioactive material packaging and transportation (P&T), nuclear facility decontamination and decommissioning, low-pollutant combustion technologies, APL P&T ( E-Program-GS PAD)
Stan Fong 925-423-3252 Regulatory compliance with DOE, LLNL, and California state requirements, safety basis documentation, hazard and accident analysis
Henry Hsieh 925-422-4541 Computer model verification, validation and calibration, quantification of margin and uncertainty, sensitivity analysis, design and analysis of computer experiments, structural analysis/optimization
Hesham Khater 925-422-2620 Radiation transport methods, safety analysis for fusion facilities/experiments, shielding analysis and operation oversight for particle accelerators and synchrotron light sources
Chan Pang 925-422-8332 System engineering and statistical analysis for nuclear material management, gamma spectroscopic analysis, risk assessment of nuclear facilities
Shiva Sitaraman 925-424-6806 Safety reviews for shielding and criticality safety compliance for packaging and transportation of radioactive materials, radiation transport methods, nuclear safeguards technology for spent fuel verification




Core Competencies


Strengths

  • Radiation Transport – simulation of radiation environment, shielding and safety analysis, radiation protection, radiation damage assessment
  • Safety Reviews for Radioactive Material Packaging and Transportation – shielding analysis, criticality safety, containment analysis
  • Hazard and Accident Analysis - regulatory compliance with DOE, LLNL, and California state requirements, safety basis documentation
  • Nuclear Material Management- gamma spectroscopic analysis, NDA data statistical analyses
  • Design and Analysis of Computer Experiments - computer model verification, validation and calibration, quantification of margin and uncertainty, sensitivity analysis
  • Nuclear Safeguards Technology - methodology development for spent fuel verification

Sample Current and Recent Efforts

  • Simulation of prompt dose in the NIF
  • Simulation of the post shot radiation environment in the NIF
  • Shielding, criticality safety and containment reviews of an addendum to the model 10-160B cask with special contents
  • Safety Analyses Review of CASTOR® THTR/AVR Pebble Bed Reactor fuel transportation casks to be shipped from the Jülich Research Center in Germany to the US
  • Review of an addendum to the RTG Package (Model 9904) SARP, and submitted Technical Review Report to DOE EM-33
  • Publication of a comprehensive report on bounding quantities of actinides and gamma sources that are shippable in modern DOE packagings-report available of P&T DOE website RAMPAC
  • Software development for a gross defect detection tool for use at the Atucha-1 spent nuclear fuel pool in Argentina – a journal article submitted to Nuclear Technology
  • Coordinating efforts to identify regulatory commitments covering environmental compliance, permitting, and emergency preparedness for high priority GS "Turf Finder" project
  • Developing SBD implementation requiremnets for continued and new operation
  • Provided system engineering and statistical analysis to the Materials Management Group in support of MC&A program for nuclear material accountability
  • Gamma-ray spectroscopic analysis in support of the WC&I program execution
  • Development of an innovative method in assessing parameters sensitivity of highly complicated High-Z materials computational model
  • Development of a UQ framework to quantify the effect of High-Z strength models on the device performance
  • W80 model form uncertainty assessment – quantify and extrapolate model form uncertainty
  • Development and validation of continuum model of a repetitive octet-truss lattice