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BURNUP DETERMINATION OF NUCLEAR FUELS. Project Report for the Quarter, April 1--June 30, 1968 and Final Report
None
Date:
March 1, 1969
Creator:
Lisman, F. L.; Maeck, W. J.; Rein, J. E.; Foster, Jr., R. E.; Abernathey, R. M.; Delmore, Jr., J. E. et al.
Object Type:
Report
System:
The UNT Digital Library
Criteria for the Design of the Thorium Fuel Cycle Development Facility
Criteria for the conceptual design of the proposed Thorium Fuel Cycle Development Facility to be located at the Oak Ridge National Laboratory were established and are presented. In addition, conceptual layouts of the building and equipment are included. Reference fuel elements and processes that were selected as a basis for developing criteria for the facility are described. (auth)
Date:
March 1, 1962
Creator:
Irvine, A.R. & Lotts, A.L.
Object Type:
Report
System:
The UNT Digital Library
Evaluation of Heat Rejection Systems for PL-3
An investigation was made of heat rejection systems for use in the PL-3 nuclear power plant, designed for placement at Byrd Station, Antarctica. It was concluded that the glycol-coupled surface condenser and air blast cooler combination appears to be suited for PL-3 plant requirements and operating conditions. (auth)
Date:
March 1, 1962
Creator:
Thurnau, C. J.
Object Type:
Report
System:
The UNT Digital Library
Nuclear magnetohydrodynamic power plant in space. [URANIUM CARBIDE FUEL]
None
Date:
March 1, 1964
Creator:
Carter, J.C. & Armstrong, R.H.
Object Type:
Report
System:
The UNT Digital Library
Spent Fuel Transfer, Storage and Shipment for PL-3
In refueling development studies performed on PL-3 Phase I design, several methods of fuel transfer, storage, and shipment were investigated. An evaluation of the relative merits of the systems and designs under study, as applied to either the BWR or PWR concepts, is made and optimum designs are selected. An analysis of spent fuel shipping cask shielding requirements is presented, along with recommendations for future study in this area. (auth)
Date:
March 1, 1962
Creator:
Hauenstein, G. C. & Pomeroy, D. L.
Object Type:
Report
System:
The UNT Digital Library
[News Script: TI]
Script from the WBAP-TV/NBC station in Fort Worth, Texas relating a news story.
Date:
March 1, 1969
Creator:
WBAP-TV (Television station : Fort Worth, Tex.)
Object Type:
Script
System:
The UNT Digital Library
[News Script: Trial]
Script from the WBAP-TV/NBC station in Fort Worth, Texas relating a news story.
Date:
March 1, 1969
Creator:
WBAP-TV (Television station : Fort Worth, Tex.)
Object Type:
Script
System:
The UNT Digital Library
[News Script: Bell strike]
Script from the WBAP-TV/NBC station in Fort Worth, Texas relating a news story.
Date:
March 1, 1969
Creator:
WBAP-TV (Television station : Fort Worth, Tex.)
Object Type:
Script
System:
The UNT Digital Library
[News Script: Shaw]
Script from the WBAP-TV/NBC station in Fort Worth, Texas relating a news story.
Date:
March 1, 1969
Creator:
WBAP-TV (Television station : Fort Worth, Tex.)
Object Type:
Script
System:
The UNT Digital Library
[News Script: Sports]
Script from the WBAP-TV/NBC station in Fort Worth, Texas relating a news story.
Date:
March 1, 1969
Creator:
WBAP-TV (Television station : Fort Worth, Tex.)
Object Type:
Script
System:
The UNT Digital Library
STATUS REPORT ON LAMB WAVES
Theoretical and experimental aspects of Lamb waves are considered. These are described as body waves, or modes, which travel throughout an entire plate and are radiated from both surfaces, so that it is possible to detect Lamb waves when the receiver and sender are on opposite sides of the plate. Studies concerning applications of Lamb waves are reported in the field of nondestructive testing. (J.R.D.)
Date:
March 1, 1962
Creator:
di Novi, R.A.
Object Type:
Report
System:
The UNT Digital Library
Quarterly Status Report on LAMPRE Program for Period Ending February 20, 1962
BS>LAMPRE I. The reactor operation is discussed. A malfunction in the shim operation was found and corrective measures taken. The core reloadings and other reactor modifications are described. The results of a gamma scanning of a fuel capsule are given. Fuel and Container Development. The properties and behavior of the Core I and the materials developed for Core II are described. Corrosion tests were carried out on pure Ta containers with molten Pu-Ce-Co alloys at 750 to 900 deg C, and the results indicate that Pu-Ce-Co alloys containing less than 5 g/cm/sup 3/ Pu should be acceptable for use in LAMPRE. The crystal structures of Pu/sub 3/Co and the most Ce-rich compound in the Ce-Co system, Ce/sub 24/Co/sub 11/, were determined. Results are given for a search for ternary eutectic alloys of high U content and for an investigation of the eutectic temperatures of several binary U alloys. Corrosive tests on ceramic materials with molten Mn-Pu-U and Mn-U alloys at 900 to 1000 deg C are summarized. Critical Experiments. Specifications and status are given for PBX. Core Test Facility. The status of the Core Test Facility design is given. The sodium systems, heat dump system, and disassembly cell mockup are …
Date:
March 1, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
LABORATORY PROGRESS ON THE DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTE BY DEEP- WELL INJECTION
Results of laboratory studies on the neutralization of Purex-type wastes are reported, including the radiochemical distribution of the fission products in the precipitate and supernate and the effect of sodium and calcium neutralizations on fission-produet separation. The problem of interstitial precipitation encountered when a second incompatible liquid is injected into a formation is discussed. Results indicate a piston-iike displacement of the interstitial liquid by the injected waste with only a small zone of precipitation formed along the contacting edge. Slurry tests were performed to determine the eapacity of various geologic materials for sorption of cesium and strontium from a synthetic Purex-type waste containing carriers and tracers. The materials studied include sands, feldspars, shales, clays, and limestone. The amount of cesium sorbed was found to be a function of several variables, among which are concentration of cesium in the waste, concentration of other cations, amount and nature of the clay material, and composition and amounts of other minerals in the disposal formation. Several types of shales and clay minerals, including illite, bentonite, montmorillonite, kaolinite, halloysite, and Conasauga shale, were slurried with simulated neutralized 6 M Purex waste. Sorption of cesium ranged from 0.6 to 6.0 mg/20 g, respectively, for the various …
Date:
March 1, 1962
Creator:
Lacy, W.J.; Sealand, O.M.; Jacobs, D.G. & Struxness, E.G.
Object Type:
Report
System:
The UNT Digital Library
MANY-BODY THEORY (Based on a series of lectures given by J.R. Schrieffer)
ABS>Notes from a series of l5 lectures on many-body theory given at Argomme Nationaf Laboratory in the spring of 1961 are presented. Topics covered include: formalism of quantum field theory, Heisenberg and interaction representations, Green's functions in the many-body problem, perturbation expansion for Green's functions, high-density electron gas, and theory of superconductivity. (M.C.G.)
Date:
March 1, 1962
Creator:
Bassani, F. & Robinson, J.
Object Type:
Report
System:
The UNT Digital Library
THE DESIGN AND CONSTRUCTION OF THERMAL FLOWMETERS
A thermal flowmeter was designed and tested which will measure a wide range of flow rates for highly corrosive gases. Response to flow rate changes is fast. The pararaeters for changing the size and response to the flowmeter were evaluated. (auth)
Date:
March 1, 1962
Creator:
Kessie, R.W.
Object Type:
Report
System:
The UNT Digital Library
A STUDY OF LIQUIDS BY NEUTRON SCATTERING
A radial density-distribution function for liquids was derived with the aid of the assumption that vibrational modes exist in liquids. The distribution function was obtained only for elastically scattered neutrons. A study of si(s) curves as a function of temperature, as well as the energy distribution of the scattered neutrons, affords a way in which to construct a model describing the motion of atoms in a liquid. (auth)
Date:
March 1, 1962
Creator:
Persiani, P.J.
Object Type:
Report
System:
The UNT Digital Library
A METHOD FOR RECORDING NUCLEAR RESONANCE CAPTURE SPECTRA
A method is described for continuously varying the Van de Graaff ion beam energy while the count rate from the decay of the compound nucleus is monitored and recorded. The method utilizes a synchronous motor system to synchronize the recorder and the magnetic field control of the Van de Graaff analyzing system. Use of this method results in significant time saving in calibration of the Van de Graaff accelerator and the determination of target thicknesses. (auth)
Date:
March 1, 1961
Creator:
Jeter, T R & Baldeschwieler, J D
Object Type:
Report
System:
The UNT Digital Library
ULTRA HIGH TEMPERATURE REACTOR EXPERIMENT (UHTREX) HAZARD REPORT
UHTREX utilizes a high-temperature, He-cooled, graphite moderated reactor employing unclad, refractory fuel elements. The reactor is designed to produce a msximum thermal power of 3 Mw and a maximum exit He temperature of 2400 deg F. The purpose of the experimert is to evaluate the advantages of the simple fuel against the disadvantages of the associated operation of a contaminated coolant loop. The mechanical and nuclear design of the reactor and related apparatus are described, discussed, and evaluated from the standpoint of hazards associated with conduct of the experiment. The building design and characteristics of the site are also examined from the same standpoint. The probable effects of operational errors and component failures are studied. The conseqnences of credible accidents are not considered to be catastrophic for either operating personnel or personnel in surrounding areas. (auth)
Date:
March 1, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
SPECTRAL SHIFT CONTROL REACTOR BASIC PHYSICS PROGRAM-THEORETICAL ANALYSIS. PART I. ANALYSIS OF EXPERIMENTS
The data obtained in the series of SSCR experiments and the theoretical analysis of the results demonstrate the spectral shift control principle clearly. The critical assemblies show that considerably larger amounts of fuel can be loaded into a core moderated with a mixture of D/sub 2/O and H/sub 2/O than in one moderated with H/sub 2/O alone. The measured Cd ratios and the calculated neutron balances show that the excess reactivity associated with this extra mass is held up in the resonance absorption of the fertile material. This leads to a higher conversion ratio system than the same sized lattice controlled by thermal neutron poison. Very good agreement is obtained between experimental and theoretical values for nearly all important parameters over the entire range of D/ sub 2/O concentration in the moderator. This agreement confirms the use of the BPG-four-group treatment, and demonstrates the calculation of reactor criticality and other measured integral parameters from fundamental cross sections without the use of intermediate fitting functions. The reactor leakage part of the calculational model is shown to be accurate by the good agreement obtained between calculated and experimental values of age, criticality, change of criticality with moderator height, and the comparison between …
Date:
March 1, 1962
Creator:
Wehmeyer, D.B.; Doederlein, J.M.; Roach, K.E. & Wittkopf, W.A.
Object Type:
Report
System:
The UNT Digital Library
Chemical Technology Division, Unit Operations Section Monthly Progress Report, August 1961
Engineering studies of a 6-in.-ID countercurrent foam column were started. The capacity of Mark II Stacked Clone Contactor was found to be limited by gradually increasing entrainment. Thoria sols were prepared from trough denitrator products in a conical bottom tank agitated by circulation through an external centrifugal pump. Experimental results agreed favorably with predicted results for the reaction of CO with CuO and fur the simultaneous reactions of H/ sub 2/ and CO with CuO. In a 2-in. dissolver, Modified Zirflex dissolution rates of Zircaloy-2 increased non-linearly with F/S. The 250-ton prototype shear was received and installed. Priorities were established for development work on graphite fuels. A total of 5 SR Core I fuel clusters were mechanically dejacketed from the second carrier shipment of SRE Core I fuel. Degradation of NaK to a solid or waxy form required that the slugs be ejected by the jackscrew. The NaK disposal system operated satisfactorily for the Iast ~3000 ml of NaK. A procedure for estimating the temperature rise of spent reactor fuels during shipping gives reasonably good results. A puIse column was operated with the light phase c nt-nuous using an external phase separator. Zirconium ates were dissolved by HF in molten …
Date:
March 1, 1962
Creator:
Whatley, M. E.; Haas, P. A.; Horton, R. W.; Ryon, A. D.; Suddath, J. C. & Watson, C. D.
Object Type:
Report
System:
The UNT Digital Library
Annual Progress Report on Fuel Element Development for Fiscal Year 1961
Progress in fuels and materials development is summarized. Major areas of investigation include a materials study by means of sample fuel plates containing uranium alloys or cermets, burnable poisons, non-uniform fuel and poison distributions and clad with various aluminum alloys; and an engineering study of fuel element geometries optimized in heat transfer, hydraulics, and materials strength. Up to 45 wt% U-Al alloys, 6 to 65 wt% UO/-Al and U3O6-Al dispersions, including enrichments ranging from 20% to 93%, were tested to 70% burnup in de-ionized water at 200 deg F in the MTR. Their performance at higher temperature is still being investigated. Test results for the MTR conditions indicate that all of the compositions investigated to date will successfully withstand even the longest irradiation at these conditions if properly fabricated. Some high strength aluminum alloy claddings, not yet fully tested, show some peculiar surface effects which may be related to corrosion. Metallographic studies of irradiated cermets reveal a reaction'' (diffusion) zone produced around UO/sub 2/ particles in contact with aluminum. These zones are being studied by means of x-ray diffraction, electron microscopy, and electron microprobe analysis. From engineering studies has come promise of improved heat removal and lower pumping requlrements for …
Date:
March 1, 1962
Creator:
Gibson, G. W. & Shupe, O. K.
Object Type:
Report
System:
The UNT Digital Library
DEVELOPMENT OF PLUTONIUM-BEARING FUEL MATERIALS. Monthly Progress Letter for Month of February 1962
Major effort during the report period was directed toward the in-pile testing program. Component PuO/sub 2/ and UO/sub 2/ powder blending trials were continued along with coprecipitated powder characterization studies. Arrangements for irradiation of short exposure rabbit capsules were made. (J.R.D.)
Date:
March 1, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Air Pulser for H-1 Column
Studies the prototype and production air pulse units.
Date:
March 1, 1961
Creator:
Bruns, L.E.
Object Type:
Report
System:
The UNT Digital Library
SUMMARY OF HRT RUNS 22, 23 AND 24
In runs 22, 23, and 24 the HRT was operated with downward flow through the core at powers up to 5 Mw. Because of leakage past the lower core tank patch, uranium could not be prevented from entering tbe blanket, so the concentration was deliberately kept above 1 g U/kg D/sub 2/O. The core power was about 0.6 of the total. Nuclear power fluctuations were larger than with upward core flow, and the cause was investigated intensively in run 22 at powers up to 1.8 Mw. Run 22 was terminated after 778 hours when a leak developed in a fuel feed pump weld. In run 23 the power was ratsed stepwise to 5 Mw. This run was terminated after 794 hours by the removal of the fuel, containing the fission and corrosion products accumulated in 10,028 hours of operation. Fuel replacement required three days. Run 24 operations were hampered by a leak which developed between the feed and letdown streams in the fuel letdown heat exchanger. The run was terminated after 546 hours, when a crack developed in a fuel feed line tee and leaked solution into the reactor cell. The changes in the core flow and heat transfer were …
Date:
March 1, 1962
Creator:
Bauman, H.F.; Buchanan, J.R.; Engel, J.R.; Haubenreich, P.N. & Richardson, D.M.
Object Type:
Report
System:
The UNT Digital Library