Remote Spent Fuel Handling in France at the La Hague Cask Unloading Facility
French policy for the back end of fuel cycle is based on spent fuel reprocessing. Irradiated spent fuels are transferred in casks from the nuclear reactors to the reprocessing plant where...
Application of Discrete Event Simulation to MRS Design
The application of discrete event simulation to the Monitored, Retrievable Storage (MRS) material handling operations supported the MRS conceptual design effort and established a set of...
Conceptual Design of a Monitored Retrievable Storage Facility
In order to achieve timely acceptance of spent nuclear fuel into the federal radioactive waste management system and to limit the amount of additional at-reactor storage capacity that...
Demonstration of a Transportable Storage System for Spent Nuclear Fuel
The ultimate disposal of spent nuclear fuel is a major issue that continues to plague the nuclear industry and the Department of Energy (DOE). In an effort to resolve some of the outstanding...
System Impacts on MRS Operations
This paper describes the results of analyses conducted to evaluate impacts on monitored retrievable storage (MRS) operations and design resulting from possible changes in the CRWMS Reference...
Human Factors Engineering Applications to the Cask Design Activities of the Civilian Radioactive Waste Management Program
The use of human factors engineering (HFE) in the design and use of spent fuel casks being developed for the Department of Energy's Civilian Radioactive Waste Management Program is addressed....
Reliability Modeling of an Engineered Barrier System
The Weibull distribution is widely used in reliability literature as a distribution of time to failure, as it allows for both increasing failure rate (IFR) and decreasing failure rate...
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,...
Optimizing Human Reliability: Mock-Up and Simulation Techniques in Waste Management
This presentation describes an ongoing effort to incorporate human factors principles into the design and process development for waste management programs at a nuclear weapons plant....
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...
Experimental Synthesis of Crystalline Matrices Based on Ce, Ba, Sr Zirconates for Immobilization of High-Level Radioactive Actinides
Experimental investigations are carried out at the Radium Institute to create different by their properties crystalline matrices, alternative to SYNROC, for incorporation of partitioned...
Assessments of System Impacts of Spent Fuel Thermal Characteristics and Emplacement Rates
Analyses conducted to evaluate the impacts spent fuel thermal characteristics and emplacement rates might have on the thermal conditions in a candidate geologic repository at the Yucca...
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...
Evaluation of Neutron Emission from Vitrified HLW Compositions
Neutron radiological hazards from vitrified HLW are important for handling and transportation - especially if the concept of separate storage of concentrated transuranics is adopted, as...
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...
Non-Fuel Bearing Hardward Melting Technology
Battelle has developed a portable hardware melter concept that would allow spent fuel rod consolidation operations at commercial nuclear power plants to provide significantly more storage...
Return to search