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Phase Stability of Homogenous Reactor Hot Fuel Solutions

Description: Portions of two samples of HRT fuel solutions were sealed in silica capillary tubes approximately three weeks after they were removed from the reactor and the temperature at which each solution separated into two liquid layers was determined.This report gives the results of these observations.
Date: August 18, 1959
Creator: Barton, C. J.; Gill, J. S.; Hebert, G. M.; Marshall, W. L. & Moore, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reprocessing of ARE Fuel, Volatility Pilot Plant Runs E-3 Through E-6

Description: The Fluoride Volatility Process was developed to recover uranium from fused salt reactor fuels. After two testing runs had been completed processing was interrupted because of a UF6 leak. After all faulty connections and seals had been made gas-tight, processing of the ARE fuel was resumed and carried to completion. This report covers processing of the ARE fuel through the last four runs plus a summary of the entire ARE reprocessing program.
Date: August 26, 1959
Creator: Whitmarsh, C. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Feasibility Study - Use of Small-Diameter Wires in UO2 Pellets For In-Pile Temperature Monitoring

Description: The feasibility of using small-diameter wires strategically placed at various radial locations in UO2 pellets for measurement of temperatures in in-pile experiments was studied. Since metals appear to be generally reactive with UO2 at very high temperatures, the use of small-diameter wires for temperature monitoring does not appear to be a promising experimental technique.
Date: October 23, 1959
Creator: Meadows, R. E. & Thurber, W. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effect Of Excess Acid On Two-Liquid-Phase Temperature Limits For the Homogeneous Reactor Fuel Solution And Its Concentrates

Description: Temperatures are given at which a second liquid phase forms in synthetic homogeneous reactor fuel solutions containing 0.0166, 0.0234, 0.0308, and 0.0413 molar excess acid and concentrates of these solutions. The result is a two-liquid-phase temperature-concentration factor curve for each original solution with minimum temperatures of 305, 322, 330 and 342'C. The minimum temperatures are considered significant in reactor operation. Interpolated two-liquid-phase temperature-concentration factor … more
Date: November 9, 1959
Creator: Moore, R. E. & Marshall, W. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Power Burst Facility (PBF) Severe Fuel Damage Test 1-4: Test Results Report

Description: "A description and evaluation of the major phenomena, based upon the response of on-line instrumentation, analysis of fission product and aerosol data, postirradiation examination of the fuel bundle, and calculations using the SCDAP/RELAP5 computer code, are presented"
Date: April 1989
Creator: Petti, D. A.; Martinson, Zoel R.; Hobbins, Richard R.; Allison, C. M.; Carlson, E. R.; Hagrman, Donald L. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department

[Appendix C-SFD 1-4 Concentration Data, Steamline]

Description: Scatter plots of isotopic concentrations from steamline detectors derived from Test Severe Fuel Damage (SFD) 1-4 gamma-ray spectral analysis showing measurement time (in seconds) on the x-axis and concentration for each isotope on the y-axis.
Date: April 1989
Creator: Petti, D. A.; Martinson, Zoel R.; Hobbins, Richard R.; Allison, C. M.; Carlson, E. R.; Hagrman, Donald L. et al.
Item Type: Refine your search to only Dataset
Partner: UNT Libraries Government Documents Department

[Appendix J-SCDAP/RELAP5 Analysis Model: Code Calculations]

Description: Document listing code calculations used for SCDAP/RELAP5 models, which has been designed to characterize fuel damage processes in a reactor vessel during severe accidents (see pages J-1 to J-4 of report).
Date: April 1989
Creator: Petti, D. A.; Martinson, Zoel R.; Hobbins, Richard R.; Allison, C. M.; Carlson, E. R.; Hagrman, Donald L. et al.
Item Type: Refine your search to only Dataset
Partner: UNT Libraries Government Documents Department

[Appendix C-SFD 1-4 Concentration Data, Gasline]

Description: Scatter plots of isotopic concentrations from gasline detectors derived from Test Severe Fuel Damage (SFD) 1-4 gamma-ray spectral analysis showing measurement time (in seconds) on the x-axis and concentration for each isotope on the y-axis.
Date: April 1989
Creator: Petti, D. A.; Martinson, Zoel R.; Hobbins, Richard R.; Allison, C. M.; Carlson, E. R.; Hagrman, Donald L. et al.
Item Type: Refine your search to only Dataset
Partner: UNT Libraries Government Documents Department

[Appendix C-DARS Data Plots from Test SFD 1-4]

Description: Graphs showing plots of the qualified Power Burst Facility (PBF) Data Acquisition and Reduction System (DARS) data from Test Severe Fuel Damage (SFD) 1-4 performed at the Idaho National Engineering Laboratory. Qualified data is shown as a solid line and trend data appears as a dashed line (see page C-16 of report). Time (in seconds) appears on the x-axis and pressure (MPa) appears on the y-axis.
Date: April 1989
Creator: Petti, D. A.; Martinson, Zoel R.; Hobbins, Richard R.; Allison, C. M.; Carlson, E. R.; Hagrman, Donald L. et al.
Item Type: Refine your search to only Dataset
Partner: UNT Libraries Government Documents Department

[Appendix C-SFD 1-4 Concentration Data, Main Floor]

Description: Scatter plots of isotopic concentrations from main floor detectors derived from Test Severe Fuel Damage (SFD) 1-4 gamma-ray spectral analysis showing measurement time (in seconds) on the x-axis and concentration for each isotope on the y-axis.
Date: April 1989
Creator: Petti, D. A.; Martinson, Zoel R.; Hobbins, Richard R.; Allison, C. M.; Carlson, E. R.; Hagrman, Donald L. et al.
Item Type: Refine your search to only Dataset
Partner: UNT Libraries Government Documents Department
open access

The Beckman 7C Thermal Cell (Hydrogen Monitor) Experiments

Description: Report describing small-scale laboratory experiments using a Beckman model 7C thermal conductivity cell conducted in order to provide a better understanding of the response of the hydrogen monitor during Power Burst Facility (PDF) Severe Fuel Damage (SFD) tests (p. 1).
Date: April 1989
Creator: Petti, D. A.; Carboneau, M. L; Martinson, Zoel R.; Hobbins, Richard R.; Allison, C. M.; Carlson, E. R. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department

[Appendix C-SFD 1-4 Concentration Data, Liquidline]

Description: Scatter plots of isotopic concentrations from liquidline detectors derived from Test Severe Fuel Damage (SFD) 1-4 gamma-ray spectral analysis showing measurement time (in seconds) on the x-axis and concentration for each isotope on the y-axis.
Date: April 1989
Creator: Petti, D. A.; Martinson, Zoel R.; Hobbins, Richard R.; Allison, C. M.; Carlson, E. R.; Hagrman, Donald L. et al.
Item Type: Refine your search to only Dataset
Partner: UNT Libraries Government Documents Department
open access

Maritime Loop Irradiation Program Savannah I Fuel Irradiation Quarterly Progress Report: January 1, 1962 -March 31, 1962

Description: This report covers the S-I-5-B-M fuel irradiation in the GETR Maritime Loop during the third quarter of fiscal year 1962. The data are summarized in tabular form in Section II. Discussions on fuel performance, fuel environment (water chemistry), and loop operations are included.
Date: April 30, 1962
Creator: Danielson, D. W. & Gilbert, R. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

High Performance UO2 Program Quarterly Progress Report Number 2: July-September 1961

Description: The primary purpose of this joint USAEC-Euratom program is to obtain a better understanding if the maximum achievable operating characteristics of UO2 as a reactor fuel. During the program work will be performed in two areas that have been of concern to reactor core designers for a long time, namely fission gas release and central melting in fuel rods.
Date: October 1, 1961
Creator: Weidenbaum, B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

High Performance UO2 Program Third Quarterly Progress Report: October-December 1961

Description: The primary purpose of this joint USAEC-Euratom program is to obtain a better understanding of the maximum achievable operating characteristics of UO2 as a reactor fuel. During the program work will be performed in two areas that have been of concern to reactor core designers for a long time, namely, fission gas release and central melting in fuel rods.
Date: January 2, 1962
Creator: Weidenbaum, B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A Study of the Fuel Value of Plutonium

Description: The fuel value of mixtures of plutonium isotopes has been calculated for five thermal reactors (Yankee, Dresden, Hallam, GCR-II, Carolinas-Virginia)
Date: February 11, 1960
Creator: Jaye, S.; Bennett, L. L. & Lietzke, M. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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