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  Partner: UNT Libraries Government Documents Department
 Decade: 1980-1989
 Language: English
Conceptual Design of a Rapid-Cycling Synchrotron for the KFA-Juelich Spallation Neutron Source

Conceptual Design of a Rapid-Cycling Synchrotron for the KFA-Juelich Spallation Neutron Source

Date: January 1983
Creator: ANL-KFA Study Group
Description: An accelerator group was established at ANL by the request of KFA-Juelich to carry out a conceptual design study and cost estimate for a rapid-cycling synchrotron as a possible first stage program on spallation neutron sources at KFA-Juelich. This set of notes is the individual notes which form the basis of the final report under this proposal prepared in January 1983. This document contains 37 papers/notes for Advanced Accelerator Development - Neutron Source Series Notes...numbered AAD-N-1 through AAD-N-37. Each note or paper is written by various authors.
Contributing Partner: UNT Libraries Government Documents Department
Optical simulation for imaging reconnaissance and intelligence sensors OSIRIS: High fidelity sensor simulation test bed; Modified user`s manual

Optical simulation for imaging reconnaissance and intelligence sensors OSIRIS: High fidelity sensor simulation test bed; Modified user`s manual

Date: January 4, 1988
Creator: Abernathy, M.F. & Puccetti, M.G.
Description: The OSIRIS program is an imaging optical simulation program which has been developed to predict the output of space-borne sensor systems. The simulation is radiometrically precise and includes highly realistic laser, atmosphere, and earth background models, as well as detailed models of optical components. This system was developed by Rockwell Power Services for the Los Alamos National Laboratory. It is based upon the LARC (Los Alamos Radiometry Code, also by Rockwell), and uses a similar command structure and 3d coordinate system as LARC. At present OSIRIS runs on the Cray I computer under the CTSS operating s stem, and is stored in the OSIRIS root directory on LANL CTSS mass storage.
Contributing Partner: UNT Libraries Government Documents Department
Stressmeter placement at spent fuel test in climax granite

Stressmeter placement at spent fuel test in climax granite

Date: May 20, 1980
Creator: Abey, A.E. & Washington, H.R.
Description: Vibrating wire stressmeters were installed in the Spent Fuel Facility at the Nevada Test Site. These stressmeters will measure the changes in in situ stress during the five-year spent fuel test. Before installation, laboratory tests were conducted to study reproducibility of placement and to develop a program hopefully to reduce corrosion of the stressmeters while in place at the Spent Fuel Facility. These laboratory tests are discussed along with the installation of the stressmeters at the Spent Fuel Facility.
Contributing Partner: UNT Libraries Government Documents Department
Stress corrosion cracking tests on high-level-waste container materials in simulated tuff repository environments

Stress corrosion cracking tests on high-level-waste container materials in simulated tuff repository environments

Date: June 1, 1986
Creator: Abraham, T.; Jain, H. & Soo, P.
Description: Types 304L, 316L, and 321 austenitic stainless steel and Incoloy 825 are being considered as candidate container materials for emplacing high-level waste in a tuff repository. The stress corrosion cracking susceptibility of these materials under simulated tuff repository conditions was evaluated by using the notched C-ring method. The tests were conducted in boiling synthetic groundwater as well as in the steam/air phase above the boiling solutions. All specimens were in contact with crushed Topopah Spring tuff. The investigation showed that microcracks are frequently observed after testing as a result of stress corrosion cracking or intergranular attack. Results showing changes in water chemistry during test are also presented.
Contributing Partner: UNT Libraries Government Documents Department
Effect of gamma radiation on groundwater chemistry and glass leaching as related to the NNWSI repository site

Effect of gamma radiation on groundwater chemistry and glass leaching as related to the NNWSI repository site

Date: May 1, 1986
Creator: Abrajano, T.; Bates, J.; Ebert, W. & Gerding, T.
Description: To address the effect of ionizing radiation on groundwater chemistry and waste form durability, NNWSI is performing an extensive set of experiments as a function of dose rate (2 x 10{sup 5}, 1 x 10{sup 4}, 1 x 10{sup 3}, and 0 rad/h). The results of the tests done at 2 x 10{sup 5} rad/h have been reported, while the 1 x 10{sup 3} and 0 rad/h tests are in progress. This paper presents an overview of the results of the tests done at 1 x 10{sup 4} rad/h and discusses the relevance of these tests to repository conditions. An interpretation of the results relating to the manner by which the glass waste form corrodes is presented elsewhere. A complete discussion of the effect of gamma radiation on groundwater chemistry and waste form durability will be presented when the series of experiments are complete.
Contributing Partner: UNT Libraries Government Documents Department
Transport and reaction kinetics at the glass:solution interface region: Results of repository-oriented leaching experiments

Transport and reaction kinetics at the glass:solution interface region: Results of repository-oriented leaching experiments

Date: December 31, 1986
Creator: Abrajano, T.A. Jr. & Bates, J.K.
Description: Repository-oriented leaching experiments involving Savannah River Laboratory (SRL) 165 type glass under a {gamma}-radiation field (1 = 0.2 x 10{sup 4} R/h) have been performed by the Nevada Nuclear Waste Storage Investigations (NNWSI) project. In this communication, we discuss glass surface analyses obtained by SEM, nuclear resonance profiling, and SIMS together with leachate solution data in relation to a mechanism that couples diffusion, hydrolysis (etching and gelation), and precipitation to qualitatively describe the release of different glass components to the leachant solutions. The release of mobile (e.g., Li) and partly mobile (e.g., B) species is controlled primarily by interdiffusion with water species across the interdiffusion zone. Glass components that are immobile in the interdiffusion zone are released to the solution by etching. For prediction of long-term steady-state concentrations of glass components with low solubility, the relative rates of release from the glass and secondary mineral precipitation must be taken into account.
Contributing Partner: UNT Libraries Government Documents Department
The reaction of glass during gamma irradiation in a saturated tuff environment: Part 3, long-term experiments at 1 x 10{sup 4}rad/hour

The reaction of glass during gamma irradiation in a saturated tuff environment: Part 3, long-term experiments at 1 x 10{sup 4}rad/hour

Date: February 1, 1988
Creator: Abrajano, T.A. Jr.; Bates, J.K.; Gerding, T.J. & Ebert, W.L.
Description: Savannah River Laboratory 165 type glass was leached with equilibrated J-13 groundwater at 90{degree}C for times up to 182 days. These experiments were performed as part of an effort by the Nevada Nuclear Waste Storage Investigations Project to assess the importance of radiation effects on repository performance and waste glass corrosion. The gamma radiation field used in this work was 1. 0 +- 0.2 x 10{sup 4} rad/h. Glass dissolution is notably incongruent throughout the entire experimental periods and normalized releases follow the sequence Li {ge} Na {ge} B {approx_equal} U {ge} Si. The normalized leach rates of these elements, as well as the measured growth rates of the reaction layers, decreased with time. The only significant variation observed in the abundance of anions is the systematic decrease in NO{sub 3}/sup {minus}//NO{sub 2}/sup {minus}/ ratio from the starting EJ-13 groundwater to the EJ-13 blank experiments to the tuff- and glass-containing experiments. A leaching model that is consistent with the observed solution data and depth profiles is presented. The applicability and limitation of the present results in predicting the actual interactions that may occur in the NNWSI repository are discussed. 35 refs., 30 figs., 12 tabs.
Contributing Partner: UNT Libraries Government Documents Department
Reaction of Glass During Gamma Irradiation in a Saturated Tuff Environment, Part 3: Long-Term Experiments at 1x10^4 Rad/Hour

Reaction of Glass During Gamma Irradiation in a Saturated Tuff Environment, Part 3: Long-Term Experiments at 1x10^4 Rad/Hour

Date: February 1988
Creator: Abrajano, Teofilo Aniag; Bates, John K.; Gerding, Thomas J. & Ebert, William L.
Description: Report on experiments to assess the importance of radiation effects on waste glass corrosion. This third part contains a description of the experiments, results, and discussion, with conclusions and related appendices.
Contributing Partner: UNT Libraries Government Documents Department
Sodium Waste Technology : a Summary Report

Sodium Waste Technology : a Summary Report

Date: January 1987
Creator: Abrams, C. S. & Witbeck, L. C.
Description: The Sodium Waste Technology (SWT) Program was established to resolve long-standing issues regarding disposal of sodium-bearing waste and equipment. Comprehensive SWT research programs investigated a variety of approaches for either removing sodium from sodium-bearing items, or disposal of items containing sodium residuals. The most successful of these programs was the design, test, and the production operation of the Sodium Process Demonstration Facility at ANL-W. The technology used was a series of melt-drain-evaporate operations to remove nonradioactive sodium from sodium-bearing items and then converting the sodium to storable compounds.
Contributing Partner: UNT Libraries Government Documents Department
Fission product plateout/liftoff/washoff test plan. Revision 1

Fission product plateout/liftoff/washoff test plan. Revision 1

Date: May 1, 1988
Creator: Acharya, R. & Hanson, D.
Description: A test program is planned in the COMEDIE loop of the Commissariat a l`Energy Atomique (CEA), Grenoble, France, to generate integral test data for the validation of computer codes used to predict fission product transport and core corrosion in the Modular High Temperature Gas-Cooled Reactor (MHTGR). The inpile testing will be performed by the CEA under contract from the US Department of Energy (DOE); the contract will be administered by Oak Ridge National Laboratory (ORNL). The primary purpose of this test plan is to provide an overview of the proposed program in terms of the overall scope and schedule. 8 refs, 3 figs.
Contributing Partner: UNT Libraries Government Documents Department
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