7 Matching Results

Search Results

Advanced search parameters have been applied.
in subjects: "Isotope Separation"  
Results: 1 - 7
open access

THE FINAL DEMISE OF EAST TENNESSEE TECHNOLOGY PARK BUILDING K-33 Health Physics Society Annual Meeting West Palm Beach, Florida June 27, 2011

Description: Building K-33 was constructed in 1954 as the final section of the five-stage uranium enrichment cascade at the Oak Ridge Gaseous Diffusion Plant (ORGDP). The two original building (K-25 and K-27) were used to produce weapons grade highly enriched uranium (HEU). Building K-29, K-31, and K-33 were added to produce low enriched uranium (LEU) for nuclear power plant fuel. During ORGDP operations K-33 produced a peak enrichment of 2.5%. Thousands of tons of reactor tails fed into gaseous diffusion p… more
Date: June 27, 2011
Creator: King, David A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Experience with Palladium Diffusers in Tritium Processing

Description: Hydrogen isotopes are separated from other gases by permeation through palladium and palladium-silver alloy diffusers in the Tritium Facilities at the US Department of Energy Savannah River Site (SRS). Diffusers have provided effective service for almost forty years. This paper is an overview of the operational experience with the various diffuser types that have been employed at SRS. Alternative technologies being developed at SRS for purifying hydrogen isotopes are also discussed.
Date: January 27, 1995
Creator: Motyka, T.; Clark, E. A.; Dauchess, D. A.; Heung, L. K. & Rabum, R. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

METHOD TO TEST ISOTOPIC SEPARATION EFFICIENCY OF PALLADIUM PACKED COLUMNS

Description: The isotopic effect of palladium has been applied in different ways to separate hydrogen isotopes for many years. At Savannah River Site palladium deposited on kieselguhr (Pd/k) is used in a thermal cycling absorption process (TCAP) to purify tritium for over ten years. The need to design columns for different throughputs and the desire to advance the performance of TCAP created the need to evaluate different column designs and packing materials for their separation efficiency. In this work, co… more
Date: June 27, 2007
Creator: Heung, L; Gregory Staack, G; James Klein, J & William Jacobs, W
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Uranium Enrichment Measurements without Calibration Using Gamma Rays Above 100 keV

Description: The verification of UF{sub 6} shipping cylinders is an important activity in routine safeguards inspections. Current measurement methods using either sodium-iodide or high-purity germanium detectors require calibrations that are not always appropriate for field measurements, because of changes in geometry or container wall thickness. The introduction of the MGAU code demonstrated the usefulness of intrinsically calibrated measurements for inspections. MGAU uses the 100-keV region of the uranium… more
Date: September 27, 2001
Creator: Ruhter, W. D.; Wang, T. F. & Hayden, C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Startup and Operation of a Metal Hydride Based Isotope Separation Process

Description: Production scale separation of tritium from other hydrogen isotopes at the Savannah River Site (SRS) in Aiken, SC, has been accomplished by several methods. These methods include thermal diffusion (1957--1986), fractional absorption (1964--1968), and cryogenic distillation (1967-present). Most recently, the Thermal Cycling Absorption Process (TCAP), a metal hydride based hydrogen isotope separation system, began production in the Replacement Tritium Facility (RTF) on April 9, 1994. TCAP has bee… more
Date: February 27, 1995
Creator: Scogin, J. H. & Poore, A. S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Disposition options for {sup 233}U

Description: The United States is implementing a program to dispose of excess nuclear-weapons-usable materials--including {sup 233}U. A series of studies have identified multiple {sup 233}U disposition options, and these options are described herein. Most of the options involve adding depleted uranium containing {sup 238}U to the {sup 233}U. Converting the {sup 233}U into a mixture of <12 wt % {sup 233}U in {sup 238}U converts the weapons-usable {sup 233}U into nonweapons-usable {sup 233}U. For {sup 233}U t… more
Date: April 27, 1998
Creator: Forsberg, C.W.; Icenhour, A.S. & Krichinsky, A.M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
Back to Top of Screen