C-14 Release and Transport From a Nuclear Waste Repository in an Unsaturated Medium

doi 10.2172/138072
Full Text
Abstract

Available in full text

Date
Authors
Publisher

Office of Scientific and Technical Information (OSTI)

Related search

Release and Transport of Gaseous C-14 From a Nuclear Waste Repository in an Unsaturated Medium

Materials Research Society Symposium - Proceedings
Mechanics of MaterialsMaterials ScienceCondensed Matter PhysicsMechanical Engineering
1990English

Nuclear Waste Repository Characterization: A Spatial Estimation/Identification Approach

IFAC Proceedings Volumes
1981English

Carbon-14 in Waste Packages for Spent Fuel in a Tuff Repository

Materials Research Society Symposium - Proceedings
Mechanics of MaterialsMaterials ScienceCondensed Matter PhysicsMechanical Engineering
1986English

Engineered Barrier Development for a Nuclear Waste Repository in Basalt: An Integration of Current Knowledge

1980English

Preliminary Drift Design Analyses for Nuclear Waste Repository in Tuff

International Journal of Rock Mechanics and Mining Sciences & Geomechanics Abstracts
1991English

Copper Corrosion in Aqueous Sulfide Solutions Under Nuclear Waste Repository Conditions

Materials Research Society Symposium - Proceedings
Mechanics of MaterialsMaterials ScienceCondensed Matter PhysicsMechanical Engineering
2012English

Review of Geotechnical Measurement Techniques for a Nuclear Waste Repository in Bedded Salt

1979English

Thermohydeologic Behavior at the Potential Yucca Mountain Nuclear Waste Repository

2000English

Solute Transport in an Unsaturated Soil

PROCEEDINGS OF HYDRAULIC ENGINEERING
1996English

Amanote Research

Note-taking for researchers

Follow Amanote

© 2024 Amaplex Software S.P.R.L. All rights reserved.

Privacy PolicyRefund Policy