A Systematic Human Factors Assessment of a Department of Energy Facility
This paper presents the methodology for conducting a systematic human factors assessment of the as-built configuration of buildings at the Rocky Flats Plant (RFP). In support of this effort,...
Impact of Staffing Parameters on Operational Reliability
This paper reports on a project related to human resource management of the Department of Energy's (DOE's) High-Level Waste (HLW) Tank program. Safety and reliability of waste tank operations...
Simulated Hanford Waste: A Study of Physical Properties, Gas Retention, and Gas Generation
This study helps to establish the physical and chemical processes responsible for the generation and retention of gases within high-level waste contained in Tank 101-SY on the Hanford...
Evaluation of Spent Fuel Behavior Under Interim Storage Conditions in Russia
The nuclear power in Russia is based on three types of water cooled power reactors VVER-440, -1000 and RBMK-1000. Two fast sodium cooled reactors-prototypes BN-350 and BN-600 are in commercial...
Shielding Benchmark Calculations of Selected Spent Fuel Storage Cask Experiments
This paper describes the application of the three-dimensional Monte Carlo code MORSE-SGC, as implemented in the SCALE system calculational sequence SAS4, to the analysis of a series of...
Verification of Shielding Analysis for Spent Fuel Storage Casks
Casks of type CASTOR are used for transport and storage of spent LWR fuel assemblies. The purpose of the present work is the verification of shielding design analysis methods by application...
Effect of Lead Shielding on Small Cask Criticality
A study was performed to evaluate gamma shield effects on criticality safety for two modern legal weight truck casks. The lead gamma shield of a small spent fuel shipping cask increases...
Treatment of Non Fuel Bearing Scrap
Problems encountered with the processing of irradiated non fuel bearing components (NFBC) during several rod consolidation demonstration programs identified the need to conduct further...
Consolidating BWR Non-Fuel Bearing Components (NFBC)
Nuclear Assurance Corporation (NAC), in cooperation the with Empire State Electric Energy Research Corporation (ESEERCO) and the Electric Power Research Institute (EPRI), has been developing...
Helping a Community Control its Future: Potential Negotiating Packages and Benefits for an MRS Host
The voluntary siting process for the Monitored Retrievable Storage (MRS) facility set forth in the Nuclear Waste Policy Amendments Act (NWPAA) of 1987 provides a potential host community...
Mangling the Models: Real-Life Experiences in Voluntary Siting
Social scientists are accumulating a growing body of research to guide the development of communications models for siting controversial facilities. The models developed by our social...
Feasibility Assessment Grants in Support of Volunteer Siting of a Monitored Retrievable Storage Facility
The Monitored Retrievable Storage facility (MRS) is an integral component of the planned Federal radioactive waste management system. The MRS will temporarily store spent fuel from commercial...
Trying to Make an Unwanted Facility Palatable
Finding suitable accommodations for the temporary storage and permanent disposal of this nation's low- and high-level radioactive waste is proving an ever more difficult task in this era...
Neptunium Retardation with Tuffs and Groundwaters from Yucca Mountain
The retardation of neptunium was studied using batch sorption and column techniques. Pure mineral separates, tuffs and groundwaters from Yucca Mountain were used for these experiments....
Dependence of Radionuclide Sorption on Sample Grinding Surface Area, and Water Composition
Experiments are described that were designed to quantify the dependence of sorption properties and surface area on the crushed-particle size of the rock samples used in batch sorption...
Research at Howard University on Retardation of Radionuclides by Sorption Processes During Host Rock?Ground Water Interactions
Extensive sorption measurements were made over a period of several years, of major radionuclides in J-13 Well water with Yucca Mountain tuff samples. Most of these measurements were single...
Diffusion of Sorbing and Non-Sorbing Radionuclides
Diffusion is considered one of the most important retardation mechanisms in fractured media. The diffusion experiments conducted involved solid tuff and groundwater from Yucca Mountain....
Surface Complexation Model Prediction of Np and Pu Distribution Coefficients
Robust estimates of radionuclide sorption coefficients (Kd) are needed to estimate radionuclide retardation during ground-water transport from a...
The SECO Suite of Codes for Site Performance Assessment
Modeling for performance assessment of the Waste Isolation Pilot Plant (WIPP) has led to development of the SECO suite of codes for groundwater flow, particle tracking, and transport....
Groundwater Flow Modelling for the TVO-92 Safety Analysis of Spent Fuel Disposal
The TVO-92 safety analysis of spent fuel disposal is based on preliminary site investigations carried out at five sites in Finland between 1987 and 1992. Groundwater flow analyses have...
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