12 Matching Results

Search Results

Advanced search parameters have been applied.
in creator/contributor: "Cleve, J"  
Results: 1 - 12
open access

Recovery of perchloroethylene scrubbing medium generated in the refabrication of high-temperature gas-cooled reactor fuel

Description: During the refabrication of high-temperature gas-cooled reactor (HTGR) fuel, perchloroethylene (C/sub 2/Cl/sub 4/) is used as the nonmoderating scrubbing medium to remove condensable hydrocarbons, carbon soot, and uranium-bearing particulates from the off-gas streams. The process by which the contaminated perchloroethylene is recycled is discussed.
Date: November 1, 1976
Creator: Judd, M. S.; Van Cleve, J. E. Jr. & Rainey, W. T. Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Implementation and assessment of turbine wake models in the Weather Research and Forecasting model for both mesoscale and large-eddy simulation

Description: Flow dynamics in large wind projects are influenced by the turbines located within. The turbine wakes, regions characterized by lower wind speeds and higher levels of turbulence than the surrounding free stream flow, can extend several rotor diameters downstream, and may meander and widen with increasing distance from the turbine. Turbine wakes can also reduce the power generated by downstream turbines and accelerate fatigue and damage to turbine components. An improved understanding of wake fo… more
Date: March 3, 2010
Creator: Singer, M; Mirocha, J; Lundquist, J & Cleve, J
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Experience in the Fabrication of Uranium - 233 Bearing ThO2UO2 Rods in a Lightly Shielded Facility at ORNL

Description: The potential of the thorium fuel cycle for achieving low nuclear fuel costs is complicated by the presence of 232U associated with 233U formed in the reactor. The decay of the 232U daughters produces penetrating radiation making the consideration of shielding and fast process times mandatory. The construction and operation of a lightly shielded, semi remote factify, known as the Kilorrod Facility, in which fuel rods containing (Th-3 wt % 233U)O2 are fabricated, is the first step in determining… more
Date: November 1963
Creator: Van Cleve, J. E., Jr. & Lotts, A. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Design, construction, and operations experience with the SWSA 6 (Solid Waste Storage Area) Tumulus Disposal Demonstration

Description: Efforts are underway at the Department of Energy facilities in Oak Ridge to improve the performance of radioactive waste disposal facilities. An engineered disposal concept demonstration involving placement of concrete encased waste on a monitored concrete pad with an earthen cover is being conducted. The design, construction, and operations experience with this project, the SWSA 6 Tumulus Disposal Demonstration, is described. 1 fig., 1 tab.
Date: January 1, 1988
Creator: Van Hoesen, S.D.; Van Cleve, J.E.; Wylie, A.N.; Williams, L.C. & Bolinsky, J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Characterization of waste streams on the Oak Ridge Reservation

Description: The Oak Ridge Reservation (ORR) plants generate solid low-level waste (LLW) that must be disposed of or stored on-site. The available disposal capacity of the current sites is projected to be fully utilized during the next decade. An LLW disposal strategy has been developed by the Low-Level Waste Disposal Development and Demonstration (LLWDDD) Program as a framework for bringing new, regulator-approved disposal capacity to the ORR. An increasing level of waste stream characterization will be ne… more
Date: January 1, 1987
Creator: Rivera, A. L.; Osborne-Lee, I. W.; Jackson, A. M.; Butcher, B. T., Jr. & Van Cleve, J. E., Jr.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Treatment of Waste by the Molten Salt Oxidation Process at the Oak Ridge National Laboratory

Description: The Molten Salt Oxidation (MSO) process has been under development by the Energy Technology Engineering Center (ETEC) to treat hazardous, radioactive, and mixed waste. Testing of the system was done on a number of wastes to demonstrate the technical feasibility of the process. This testing included simulated intermediate level waste (ILW) from the Oak Ridge National Laboratory. The intermediate level waste stream consisted of a slurry of concentrated aqueous solutions of sodium hydroxide and so… more
Date: March 1, 1993
Creator: Crosley, S. M.; Lorenzo, D. K.; Van Cleve, J. E.; Gay, R. L.; Barclay, K. M.; Newcomb, J. C. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
Back to Top of Screen