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Designing Vitrified Clay Pipe Systems with EASE
NCPI has developed a computerized trench load design program which provides a broad and complete spectrum of design options which will enable engineers and contractors to safely design...

A Look Back in Time to Verify Life Cycle Cost Analyses
The proper engineering design of any hydraulic structure requires consideration of different but interrelated fields of: 1) Planning, 2) Hydrology, 3) Hydraulics, 4) Structural, 5) Installation,...

Field Experiment on Behavior of Continuous Water Main with a Miter Bend
A field experiment was conducted to investigate behaviors of a buried continuous steel water main with a 90-degree miter bend subjected to internal pressure and ground settlement. Deformations...

Incorporating Seismotectonic Data into Seismic Hazard Analyses
A wide range of seismotectonic data are now being incorporated into probabilistic seismic hazard analyses, supplementing the inadequately short historical seismicity record. This paper...

A Preliminary Model for Carbon-14 Transport in a Clay Buffer
A model has been developed to assess the effect of calcite dissolution and precipitation reactions on the transport of ¹⁴C through a saturated, calcite-containing...

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...

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...

Diffusion Coefficients and Hydraulic Conductivity in Unsaturated Hanford Soils and Sediments
Two groundwater transport parameters of some Hanford formation materials, the hydraulic conductivity and the diffusion coefficient, were measured to aid in predicting contaminant migration....

Reconnaissance ? ??C and ??⁸O Data from Trench 14, Busted Butte, and Drill Hole G-4, Yucca Mountain, Nevada Test Site
Trench 14 was excavated to investigate the extent of Quaternary movement on the Bow Ridge fault, a north-south structure on the east side of Yucca Mountain. The trench exposes calcite...

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...

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...

 

 

 

 

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