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Storage and release of radiation energy in salt in radioactive waste repositories

Description: The results showed that appreciable amounts of gamma-radiation energy can be stored under certain exposure conditions. The results also showed that thermally activated annealing takes place at elevated temperatures and that the rates of this annealing at temperatures above about 150/sup 0/C are such that negligible amounts of energy will be stored in salt in a repository where the salt is at temperatures above about 150/sup 0/C. We are not able to show that thermally activated annealing takes p… more
Date: October 1, 1977
Creator: Jenks, G. H. & Bopp, C. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Calorimetric Calibration of a Graphite Walled, Cavity-Type Ionization Chamber

Description: Technical report outlining cavity-type ionization chambers with graphite walls that are used to measure heat dissipation in the graphite reflector of the MTR mock-up. Studies the relationship between the ionization occurring in the chamber and the heat generated in the surrounding graphite medium. [From Abstract]
Date: January 23, 1951
Creator: Jenks, G. H.; Breazeale, W. M. & Hairston, J. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Radiation chemistry of salt-mine brines and hydrates. [Gamma radiation]

Description: Certain aspects of the radiation chemistry of NaCl-saturated MgCl/sub 2/ solutions and MgCl/sub 2/ hydrates at temperatures in the range of 30 to 180/sup 0/C were investigated through experiments. A principal objective was to establish the values for the yields of H/sub 2/ (G(H/sub 2/)) and accompanying oxidants in the gamma-ray radiolysis of concentrated brines that might occur in waste repositories in salt. We concluded that G(H/sub 2/) from gamma-irradiated brine solution into a simultaneous… more
Date: July 1, 1981
Creator: Jenks, G. H.; Walton, J. R.; Bronstein, H. R. & Baes Jr., C. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Maximum acceptable temperatures of wastes and containers during retrievable geologic storage

Description: Estimates of maximum acceptable temperatures of waste and containers during retrievable geologic storage were needed for use in evaluating and comparing conceptual designs for repositories for wastes from reprocessing and for spent fuel in several different rock types. Estimates of these temperatures and discussions of the bases for the estimates are presented.
Date: August 17, 1977
Creator: Jenks, G. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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An Experimental Study of the Performance of a Cavity Type Ionization Chamber

Description: Abstract: "Comparisons between calorimetric and ionization chamber measurements of the power generated in graphite by absorption of energetic gamma rays have been carried out. The results serve as a calibration of the chamber. They also serve to test the consistency between the theoretical performance of this type of chamber and previously determined values for the factors which relate ionization in the chamber to energy absorption in the walls."
Date: 1952
Creator: Jenks, G. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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HRP Radiation Corrosion Studies

Description: A fifth in-pile loop experiment, L-4-8, was completed. The loop operated in-pile for a total of 1637 hr, during which time the LITR energy output was 4377 Mwhr. The average fission power in the loop based o cesium analyses was 622 w when the LITR was at full power (3 Mw). Based on oxygen data, the generalized corrosion rate for the first 300 hr was 4.0 mpy; the rate for the remaining 1357 hr was 0.7 mpy. The nickel data gave parallel results. The corrosion of the type 347 stainless steel, Zirca… more
Date: August 21, 1956
Creator: Baker, J. E.; Bradley, N. C.; Jenks, G. H.; Olsen, A. R.; Savage, H. C. & Walter, F. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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In-Pile Loop Investigations of Corrosion of Zircaloy-2 and Other Possible Reactor Materials in 0.04 m UO2SO4 AT 280°C

Description: One of a series of experiments to test the radiation corrosion of Zircaloy-2 and other possible reactor construction materials in UO2SO4 solutions under various radiation intensities, temperatures, solution compositions, and velocities of flow past specimens.
Date: May 5, 1962
Creator: Jenks, G. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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In-Pile Radiation Corrosion Experiments with Zirconium, Titanium, and Steel Alloys in 0.17 m UO2SO4 Solutions at 280°C

Description: In-pile loop experiments L-2-15 and L-4-16 were two of a series designed to test the radiation corrosion of Zircaloy-2 and other possible reactor construction materials in UO2SO4 solutions under various conditions of radiation intensities, temperatures, solution compositions, and velocity flow past specimens.
Date: June 10, 1963
Creator: Jenks, G. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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In-Pile Loop Corrosion Experiments with Uranyl Sulfate Solutions at 235 and 250 C

Description: Report presenting in-pile loop experiments DD, EE, FF, GG, L-412, L-413, and L-418, which were seven of a series designed to test the radiation corrosion of zirconium, titanium, and stainless steel alloys in solutions under various conditions of radiation intensity, temperature, solution composition, and velocity of flow. Steel specimens exposed in the loop cores showed increases in corrosive attack over that expected out-of-radiation.
Date: August 15, 1963
Creator: Jenks, G. H. & Baker, J. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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HRP Radiation Corrosion Studies: In-Pile Loop L-4-11

Description: Report issued by the Oak Ridge National Laboratory discussing radiation corrosion studies. As stated in the introduction, "the purpose of this experiment was to compare the performance of a large number of materials under similar irradiation and exposure conditions" (p. 1). This report includes tables, illustrations, and photographs.
Date: June 27, 1958
Creator: McWherter, J. R. & Baker, J. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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HRT Corrosion Samples -- Additional Data on Specimens Removed Prior to Run No. 20.

Description: Results of the examinations of corrosion specimens exposed in the HRT are presented. Specimens examined included (1) core screen samples, (2) core specimen array No. 1, (3) blanket specimen array No. 2, (4) core solution line specimen arrays No. 103 and 103A, (5) blanket solution line specimen array No. 203. Complete information is still not available on all the specimens removed from the reactor, however, those data which have been accumulated are presented. These include corrosion rates, com… more
Date: February 2, 1961
Creator: Baker, J. E.; Silverman, M. D.; Jenks, G. H. & Olsen, A. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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