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Uranium hydrogeochemical and stream sediment reconnaissance data release for the Dubois NTMS Quadrangle, Idaho/Montana, including concentrations of forty-five additional elements

Description: Totals of 1024 water samples and 1600 sediment samples were collected from 1669 locations in the Dubois quadrangle. Water samples were taken at streams, springs, and wells; sediment samples were collected from streams and springs. All field and analytical data are presented for waters in Appendix I-A and for sediments in I-B. All elemental analyses were performed at the LASL. Water samples were initially analyzed for uranium by fluorometry. All water samples containing more than the upper detec… more
Date: August 1, 1980
Creator: LaDelfe, C. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reactor safety research programs. Quarterly progress report, January 1--March 31, 1977

Description: The projects reported each quarter are the following: Gas Reactor Safety Evaluation, THOR Code Development, SSC Code Development, LMFBR and LWR Safety Experiments, Fast Reactor Safety Code Validation, Technical Coordination of Structural Integrity, and Fast Reactor Safety Reliability Assessment.
Date: May 1, 1977
Creator: Romano, A. J. (comp.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Gas-cooled reactor programs: High-Temperature Gas-cooled Reactor Base-Technology Program. Annual progress report for period ending December 31, 1978

Description: Progress in HTGR studies is reported in the following areas: fission product transport and coolant impurity effects, fueled graphite development, PCRV development, structural materials, characterization and standardization of graphite, and evaluation of the pebble-bed type HTGR.
Date: June 1, 1979
Creator: Homan, F. J. & Kasten, P. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Gas-Cooled Reactor Programs. High-Temperature Gas-Cooled Reactor Base-Technology Program. Annual progress report for period ending December 31, 1977

Description: Progress in HTGR studies is reported in the following areas: fission product technology and coolant impurity effects, fueled graphite development, PCRV development, structural materials, characterization and standardization of graphite, and evaluation of the pebble-bed type HTR.
Date: July 1, 1978
Creator: Homan, F. J. & Kasten, P. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reactor safety research programs. Quarterly progress report, 1 July--30 September 1977

Description: HTGR safety evaluation included studies on fission product release; materials, chemistry, and instrumentation; structural evaluation; and analytical safety evaluation. LMFBR work included accident sequence studies, technical coordination of structural integrity, and SSC code development and validation. LWR safety studies included thermal/hydraulic analysis; THOR code development; and appraisal of analysis development in foreign countries.
Date: October 1, 1977
Creator: Kouts, H.J.C. & Kato, W.Y.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Cesium Chloride Compatibility Testing Program. Annual report, fiscal year 1984

Description: During the course of a prior examination, it was found that one of the aged test capsules exhibited discoloration and pitting on the outer surface of the inner capsule. The damage was attributed to problems encountered in the electropolishing operation, which is used to decontaminate the inner capsule after it is loaded with the CsCl and welded shut. A study was carried out in FY 1984 to: determine if the pitting was associated with the electropolishing operation; identify acceptable solution(s… more
Date: January 1, 1985
Creator: Bryan, G. H. & Divine, J. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Integrated system for production of neutronics and photonics calculational constants. Volume 15, Part E. Data testing results for the LLL Evaluated Nuclear Data Library (ENDL-78)

Description: The LLL Evaluated Nuclear Data Library (ENDL-78) was tested for validity by comparing calculated and experimental values of k/sub eff/ for 67 critical assemblies and emission neutron spectra for 22 spheres that were pulsed with 14-MeV neutrons. 22 figures, 5 tables.
Date: August 13, 1979
Creator: Howerton, Robert J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Reactor safety research programs. Quarterly progress report, October 1--December 31, 1977

Description: HTGR safety evaluation included studies on fission product release; materials, chemistry, and instrumentation; structural evaluation; and analytical safety evaluation. LMFBR safety evaluation included studies on accident sequences, technical coordination of structural integrity, and SSC code development and validation. LWR safety studies included thermal/hydraulic accident analysis, THOR code development, and stress corrosion cracking of PWR steam generator tubing.
Date: January 1, 1978
Creator: Romano, A.J. (comp.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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