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Startup and Initial Testing of SM-1 Core II With Special Components
The loading operation for SM-1 Core II is described. Results of startup physics measurements (Test A-300 (Series) and fission product iodine monitoring in the primary coolant are given. The SM-1 Core II initial loading progressed satisfactorily, fulfilling the predictions of the zero power experiment performed at the Alco Criticality Facility. The initial cold clean five rod bank position was 6.53 in.; the initial hot, no xenon, five rod bank position was 9.62 in.; the initial hot, equilibrium xenon, five rod bank position was 11.41 in.; and the initial hot, peak xenon, five rod bank position was 12.14 in. Rods A and B were 19.00 in. in all four measurements. Stuck rod measurements indicated that an adequate shutdown margin was available with 20% of the rods fully withdrawn. All rod calibrations indicated a distinct shift and broadening of the peaks when compared with similar Core I calibrations. The temperature coefficient for Core II was 3.5 cents/ deg F at 440 deg F. Equilibrium xenon was worth approximately - 00 while peak xenon was worth - 43, both relative to the hot, no xenon core condition. During the period June 2, 1961 through September 30, 1961, the reactor operated at a total …
Date:
February 28, 1962
Creator:
Moote, F. G. & Schrader, E. W.
Object Type:
Report
System:
The UNT Digital Library
A PROGRAM OF RESEARCH AND CALCULATIONS OF RESONANCE ABSORPTION. Final Report
A direct numerical integration of the integral equation for the average collision density in the absorber was previously suggested in a discussion of resonance absorption. The implementation of this program is considered. The method of calculation, comparison with experimental data, and the computer code developed are described. The method of integration, computation of cross sections, selection of mesh size, integration interval, outside correction, the Dancoff correction, and unresolved resonances are discussed. Resonance integrals for U/sup 235/ and Th2/sup >/s3>s/sup 2/ were calculated and compared with experiment. (M.C.G.)
Date:
August 28, 1961
Creator:
Nordheim, L.W.
Object Type:
Report
System:
The UNT Digital Library
[News Script: Dallas City Council]
Script from the WBAP-TV/NBC station in Fort Worth, Texas relating a news story.
Date:
October 28, 1968
Creator:
WBAP-TV (Television station : Fort Worth, Tex.)
Object Type:
Script
System:
The UNT Digital Library
[News Script: Fire]
Script from the WBAP-TV/NBC station in Fort Worth, Texas relating a news story.
Date:
December 28, 1968
Creator:
WBAP-TV (Television station : Fort Worth, Tex.)
Object Type:
Script
System:
The UNT Digital Library
Recent Developments in the Area of Religious Exercises in Public Schools and Other Public Places
This report addresses the recent developments in the area of religious exercises in public schools and other public places.
Date:
February 28, 1969
Creator:
Danner, Herbert
Object Type:
Report
System:
The UNT Digital Library
AN INVESTIGATION OF THE HIGH-TEMPERATURE PROPERTIES OF THE AISI TYPE 502 STEEL
None
Date:
November 28, 1961
Creator:
Martin, W. R. & McCoy Jr., H. E.
Object Type:
Report
System:
The UNT Digital Library
Tertiary Blast Effects: The Effects of Impact on Mice, Rats, Guinea Pigs and Rabbits. Technical Progress Report
A total of 455 mlce, rats, gulnea plgs, and rabbits was subjected to lmpact at velocitles ranglng between 25 ft/sec and 51 ft/sec. The deslred velocities were generated by allowlng the anlmals to free-fall from various helghts to a flat concrete pad. The ventral surface of each anlmal was the area of impact. Problt analyses of the 24-hr mortallty data ylelded LD/sub 50/ lmpact veloclties with 95% confldence limits as follows: mouse, 39.4 (37.4 to 42.0) ft/ sec; rat, ft/sec; and rabbit, 31.7 (30.2 to 33.3) ft/sec. The LD/sub 50/ figures for the mouse and rat were slgnificantly higher, statlstically, than those for the gulnea plg and rabblt. The small spread ln the LD/sub 50/ values suggested little variation ln the tolerance of blologlcal systems to impact. Further, the steepness of the mortallty curves lndicated a narrow survlval range to lmpact. Extrapolatlon of the experimental data to the 70 kg anlmal yielded a predicted LD/ sub 50/ impact velocity of 26 ft/sec (18 mph). Literature relevant to the human case was revlewed and the tentative appllcabllity of the predlcted flgures to adult man ls discussed. (auth)
Date:
February 28, 1961
Creator:
Richmond, D. R.; Bowen, I. G. & White, C. S.
Object Type:
Report
System:
The UNT Digital Library
REMOTELY CONTROLLED SHEARING OF PIPE AND STRUCTURAL MEMBERS
A shearing tool was developed for remotely controlled severing of pipes or structural members. The shear is rotated about its axis in a wrist motion by the pumped hydraulic fluid that also powers the shear blade. It can be used in a stationary mounting or suspended from a crane. A C-shaped support for the shear was designed to pass through a small top opening of a shielded cell. The controls for manipulating the shear pass through or along the Cframe. The shear jaw opens to 5 in. in height and 7 in. in width, and the total weight of the tool is only 575 lb. It was used to cut metal sections 4 3/4 in. thick and 4-in. sched.-40 stainless steel pipe. (auth)
Date:
December 28, 1961
Creator:
Abbatiello, A. A.
Object Type:
Report
System:
The UNT Digital Library
GAS-COOLED REACTOR PROGRAM. QUARTERLY PROGRESS REPORT FOR PERIOD ENDING JUNE 30, 1961
Activities are discussed for research in design investigations, and materials development and testing conducted in connection with the development of the EGCR. The discussions are given in terms of: reactor physics; reactor design studies; heat transfer and fluid now investigations; materials development; in- pile and out-of-pile testing of components and materials; and development of test loops and components. (B.O.G.)
Date:
August 28, 1961
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Reactor Controls Reliability and Maintenance at the ORR
Early evaluation and study of the various criteria for the ORR clearly established the requirements for the fundarnental safety and control instrumentation, and the instrumentation was well integrated into the design and construction of the plant. However, it was not designed for the optimum of maintenance convenience and minimum reactor down time in the event of instrument failure. The revisions and additions that have been made in the physical plant and maintenance which have resulted in a definite reduction of reactor down time resulting from instrument failure in the reactor and in the experiments are described. (auth)
Date:
August 28, 1962
Creator:
West, K.W.
Object Type:
Report
System:
The UNT Digital Library
Comparison of Gaseous Waste Handling Systems for PL-3
Gaseous waste handling systems are compared for direct and indirect boiling water and pressurized water reactors for PL-3 application. Areas that are common to the various concepts are not discussed since they do not enter into a comparison study. The major differences present are in the handling of active gases released to or held in the primary system coolant. These gases which could be present, their possibIe release from the system, and the necessary processing requirements are discussed in detail. Sufficient information is presented to enable one to analyze the methcds required to remove gaseous activity present in other size and type pressurized and boiIing water reactors. (auth)
Date:
February 28, 1962
Creator:
Noble, J. H. & Duke, E. E.
Object Type:
Report
System:
The UNT Digital Library
Flexible Monte Carlo Programs FMC-N and FMC-G
Flexible Monte Carlo programs FMC-N and FMC-G (GE-ANPD Programs 516 and 515) are digital computer programs which apply Monte Carlo methods to simulate neutron and gamma ray life histories, respectively, in a source-shield configuration. The programs were designed for flexlbility in the geometrical, material, nuclear, and source descriptions of source-shield configurations and variance reduction techniques. The programs were also designed to optimize the use of fast memory and to provide complete freedom in the dimensions of the various input quantities. The programs are coded for an IBM-704 computer with a fast memory capacity of 32,768 storage locations and eight magnetic tape units, and for an IBM7090 computer wlth a fast memory capacity of 32,768 storage locations and ten magnetic tape unlts on two date channels. No magnetic drum storage is necessary for either computer. (auth)
Date:
April 28, 1961
Creator:
Loechler, J. J. & MacDonald, J. E.
Object Type:
Report
System:
The UNT Digital Library
Small Power Reactor Projects of the United States Atomic Energy Commission
Information on small power reactor projects of the USAEC is summarized. General information concerning the projects as a whole is given. Specific projects discussed include: the Elk River Power Reactor, the Piqua Nuclear Power Facility, the BONUS Power Reactor, the Pathfinder Power Reactor, the small-size pressurized water power reactor, and the experimental low-power process heat reactor. (M.C.G.)
Date:
September 28, 1961
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Primary Shield Optimization Survey for the PL-3 Reactor
A detailed study of four reactor and shield configurations was made. Two basic reactor types, the boiling water and pressurized water reactors were considered. Shield materials of lead-water and iron-water were used with varying thicknesses for determining the optimum shield configuration for the PL-3 reactor. Also presented is a survey of available shielding codes. (auth)
Date:
June 28, 1962
Creator:
Scoles, J. F. & Crouch, A. N.
Object Type:
Report
System:
The UNT Digital Library
Chemical Processing Technology Quarterly Progress Report, October-December 1961
The ICPP processed Al fuel, prtncipally of the MTR-ETR type, durtng this quarter. Newly designed and installed processing equipment exhibited excellent operating performance. This included direct-air-pulsed extraction, stripping and scrub columns, and a cascade-controlled continuous evaporator in first cycle product concentration service. Aqueous zirconium fuel processing studies continued with the objective of adapting the hydrofluoric acid process to continuous dissolution-complexing to increase the capacity of the LCPP process while using as much existing equipment as possible to minimize costs. Six variations of hydrofluoric acid flowsheets were tested in a smallscale continuous dissolvers. Dissolution rates were found to be high in all cases and dissolution was easily initiated at temperatures as low as 36 deg C. Monel and Carpenter 2O(Nb) were found to be satisfactory construction materials, from the standpoint of corroston, if oxidizing conditions were carefully controlled. Additional studies are reported on the stability of blended Zr and Al process raffinates and on the nature of the solids which result from the sodium formate headend precipitation process. Electrolytic dissolution studies, dtrected at fundamentals of current utiltzation in a series''-type dissolver, demonstrated that high current utilization is obtained when the polarization resistance is small compared with the solution resistance. Factors affecting …
Date:
March 28, 1962
Creator:
Bower, J. R.
Object Type:
Report
System:
The UNT Digital Library
THE OAK RIDGE RESEARCH REACTOR (ORR), THE LOW-INTENSITY TESTING REACTOR (LITR), AND THE OAK RIDGE GRAPHITE REACTOR (OGR) AS EXPERIMENT FACILITIES
>Characteristics of the ORR, LITR, and OGR that experimenters have found to be important are listed. The results of a survey conducted among experimenters on the utility of the reactors for various types of experiments are discussed, and some changes which might be made to improve the utilization are listed. A brief outline, with references, of most of the experiments currently being performed is included. (auth)
Date:
August 28, 1962
Creator:
George, K.D.
Object Type:
Report
System:
The UNT Digital Library
Failure Analysis of Dispersion Fuel Elements Based on Matrix Cracking
A mathematical model has been developed for estimati the burnup at which mechanical failure occurs in dispersion fuel elements. It is postulated that failure at low temperature, < 900 deg F, occurs as a result of brittle fracture of an elastic matrix when the intensity of the stress locally reaches the ultimate strength of the material. The contributions of fission gas pressure and thermal stress are incorporated in the stress analysis. Because of the complexity of the stress distribution and the failure process, it was necessary to make stringent assumptions in order to have a workable model. Within the framework of the postulates, burnups to failure are predicted for several values of certain important parameters and compared with burnups to failure obtained from a plastic yield model for failure developed by previous investigation. The two models give good agreement for the special cases considered. Of the parameters examined, relative density of the fuel particles has the greatest influence on predictions of allowable burnup. The thermal stress and volume fraction of fuel play minor roles. (auth)
Date:
December 28, 1961
Creator:
Beck, S. D.
Object Type:
Report
System:
The UNT Digital Library
DEVELOPMENT OF FREEZE VALVE FOR USE IN THE MSRE
Three types of frozen-seal valves'' were tested for possible use in the MSRE. The seal was melted by direct resistance heat, by induction heat, and by clamp-on Calrod heat. The frozen seal was made in a preformed restriction section of a standard piece of pipe by a cooling-gas jet stream directed at the restriction. All three valves performed satisfactorily through 100 test cycles. The Calrodheated valve was selected for MSRE use on the basis of simplicity of design and of operation. Two of the valves are successfully undergoing further tests on the MSRE Engineering Test Loop. (auth)
Date:
February 28, 1962
Creator:
Richardson, M.
Object Type:
Report
System:
The UNT Digital Library
NON-DESTRUCTIVE ANALYSIS OF URANIUM IN GRAPHITE FUEL ELEMENTS BY NEUTRON ACTIVATION
A method is presented for the determination of uranium (as U/sup 238/) in uraniuni-loaded graphite fuel elenients by a non-destructive, direct radioactivity analysis technique. A 200-cbannel pulse-height analyzer, equipped with a 3 in. x 3 in. NaI(Tl) crystal, is used to measure the Np/sup 239/ radioactivity of the neutron-irradiated samples. The amount of U/sup 238/ in the test samples is deterimined quantitatively by comparing the Np/sup 239/ radioactivity induced in each sample with the Np/sup 239/ radioactivity induced into known standards of U/sup 238/ processed under the same conditions as the test samples. The limit of detection for U/sup 238/in samples of normal uranium composition for this method is about 1.0 x l0-4 ug. (auth)
Date:
November 28, 1961
Creator:
Bate, L.C.; Hampton, W.J. & Leddicotte, G.W.
Object Type:
Report
System:
The UNT Digital Library
[Photograph 2012.201.B0292.0155]
Photograph taken for a newspaper owned by the Oklahoma Publishing Company.
Date:
September 28, 1961
Creator:
unknown
Object Type:
Photograph
System:
The Gateway to Oklahoma History
[Photograph 2012.201.B0313.0132]
Photograph taken for a story in the Daily Oklahoman newspaper. Caption: "Mrs. Bessie Donica discusses her collection of glass insulators - a hobby still in its infancy ."
Date:
September 28, 1969
Creator:
unknown
Object Type:
Photograph
System:
The Gateway to Oklahoma History
[Photograph 2012.201.B0316.0364]
Photograph taken for a newspaper owned by the Oklahoma Publishing Company. Caption: "Assistant Chief Jack Duggan and fireman George Fina view fire scene."
Date:
November 28, 1969
Creator:
Wood, Tony
Object Type:
Photograph
System:
The Gateway to Oklahoma History
[Photograph 2012.201.B0410.0199]
Photograph taken for a story in the Oklahoma Times newspaper. Caption: "Training preparedness for natural and national emergencies and disasters will be the 1967-1968 action plan of Oklahoma City P-TA Council's civil defense committee."
Date:
September 28, 1967
Creator:
Argo, Jim
Object Type:
Photograph
System:
The Gateway to Oklahoma History
[Photograph 2012.201.B0297.0007]
Photograph taken for a story in the Daily Oklahoman newspaper. Caption: "Superintendent of Pauls Valley State School since its establishment as an institution for mentally retarded children in 1953 has been J. R. Deacon."
Date:
May 28, 1960
Creator:
unknown
Object Type:
Photograph
System:
The Gateway to Oklahoma History