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Perspectives on Out-of-Pool Spent Fuel Storage Requirements 1992-2036
The estimates of requirements for additional storage capacity for spent nuclear fuel from commercial LWRs in the United States are examined in this study. A comparison of this study's...

Throughput Rate Study
The Civilian Radioactive Waste Management System (CRWMS) Management and Operating (M&O) Contractor, has completed a study to analyze system wide impacts of operating the CRWMS...

Systems Integration and Economic Aspects of the Universal Container System
Universal containers (UC) are multi-assembly spent fuel containers that are loaded and sealed at reactor sites or the first DOE facility. They are thereafter handled as clean containers...

ATW System Impact on High-Level Waste
Criteria are developed for transmutation system impact on HLW storage that are related to intrusion and long-term risk reduction. Thermal reactor, fast reactor, and accelerator-driven,...

Nuclear Regulatory Commission Staff Development of the License Application Review Plan for a High-Level Radioactive Waste Repository
The Nuclear Regulatory Commission staff has recently started a new initiative to develop the License Application Review Plan (LARP) which the staff will use in its reviews of the U.S....

Limited Work Authorization for a Monitored Retrievable Storage Facility
The issuance of an limited work authorization (LWA) by the Nuclear Regulatory Commission (NRC/Commission) allows a potential licensee permission to undertake preliminary site construction,...

The Waste Isolation Pilot Plant (WIPP) Integrated Project Management System
The Waste Isolation Pilot Plant (WIPP), located 26 miles east of Carlsbad, New Mexico, is a research and development project of the Department of Energy (DOE), tasked with the mission...

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....

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...

 

 

 

 

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