Optimal Route Selection for High Level Nuclear Waste Transport Based Upon Radiological Risk
The purpose of this paper is to demonstrate route optimization based directly upon the minimization of radiological risk as computed from local conditions. An operational impact analysis...
PAGIS & PACOMA: Performance Evaluations of Deep Geological Disposal. Results and Conclusions
Two coordinated research projects were undertaken by the Commission of the European Communities to study the safety performances of geological radwaste disposal systems in the post-operational...
Evaluation of Near-Field Thermal Environmental Conditions for a Spent Fuel Repository in Tuff
A repository heat transfer analysis is being performed by the Pacific Northwest Laboratory (PNL)a for the U.S. Department of Energy's...
Technical Considerations and Approcah for Evaluating Substantially Complete Containment of High-Level Nuclear Waste
The current Federal Regulations, Title 10 Part 60.113(a)(1)(i)(A) require that, for at least 300 years, nuclear waste containment within a waste package shall be substantially complete....
Permeability and Dispersivity of Variable-Aperture Fracture Systems
A number of recent experiments have pointed out the need of including the effects of aperture variation within each fracture in predicting flow and transport properties of fractured media....
Thermal Stability of Zeolitic Tuff from Yucca Mountain, Nevada
Thermal models of the potential repository at Yucca Mountain, Nevada, suggest that rocks near the potential host rock will experience elevated temperatures for at least 1000 yr. In order...
Regulatory Considerations for Designing Surface Facilities for Yucca Mountain High-Level Waste Repository
This paper outlines U.S. Nuclear Regulatory Commission's (NRC's) key regulations applicable to U.S. Department of Energy's (DOE's) design...
Optimization Method for Dimensioning a Geological HLW Waste Repository
This method was developed by the CEA to optimize the dimensions of a geological repository by taking account of technical and economic parameters. It involves optimizing radioactive waste...
Evaluation of the Canadian HLW Disposal Program?Performance Assessment Aspects
The inception and development of the Canadian HLW disposal program are described, showing its basis in the multi-barrier system concept and noting the mechanisms in place for its evaluation...
A Demonstration of the Systems Integration Modeling System (SIMS) as a Decision-Support Tool
In April 1989, the Office of Civilian Radioactive Waste Management (OCRWM) Integration Branch completed major demonstration of the Systems Integration Modeling System (SIMS). That system...
Materials Selection Issues for Structural Components of Transportation Casks
Sandia National Laboratories (SNL) is evaluating the use of alternate materials (i.e. other than stainless steel) as structural components in nuclear spent fuel transportation casks. This...
Experience with Certifying Borated Stainless Steel as a Shipping Cask Basket Material
The original cask designs for a cask demonstration project featured fuel baskets constructed of borated stainless steel (bss) as a structural material. The project is intended to demonstrate...
Concrete Cask Storage Technology
The paper presents the design and operation of the new dry storage system for nuclear waste. The system was designed by complete nuclear, thermal-hydraulic and structural analysis to the...
Important Factors in Developing a Nuclear Waste Management System
The nuclear waste management system provides unique challenges for a large and diverse segment of our society. For the politician there is the blending of national policy and the interests...
Site Specific Geologic Interpretations of Richton Salt Dome
There have been numerous investigations into the geological and hydrological aspects of the Richton Salt Dome area since its selection as a preferred site for a nuclear waste repository....
Postclosure Safety Assessment of Radioactive Waste Disposal Systems: Current State of Understanding and International Consensus
Approximately ten years have passed since the first comprehensive safety assessments of radioactive waste disposal systems appeared. Through intensive efforts in practically all countries...
Data Quality Assurance Controls Through the WIPP in Situ Data Acquisition, Analysis, and Management System
Assurance of data quality for the in situ tests fielded at the Waste Isolation Pilot Plant is of critical importance. These tests supply the information for development and verification...
Systems Integration Operations/Logistics Model (SOLMOD)
SOLMOD is a discrete event simulation model written in FORTRAN 77 and operates in a VAX or PC environment. The model emulates the movement and interaction of equipment and radioactive...
A Systems Engineering Cost Analysis Capability for Use in Assessing Nuclear Waste Management System Cost Performance
The System Engineering Cost Analysis (SECA) capability has been developed by the System Integration Branch of the U.S. Department of Energy's Office of Civilian Radioactive...
Method for Determining the Fuel Contribution to the Source Term in Trasnport Casks
A comprehensive source term characterization methodology has been developed for the determination of the fuel contribution to the potentially releasable radioactivity in spent fuel shipping...
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