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Startup and Initial Testing of SM-1 Core II With Special Components

Description: 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 … more
Date: February 28, 1962
Creator: Moote, F. G. & Schrader, E. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Measurements and Changes on SM-1 Core II During Period October 1, 1961 to May 30, 1962

Description: Tests at the SM-1 reactor are reported for the period October 1, 1961, to May 31, 1962. Loading changes were made in SM-1 Core II during the scheduled semiannual shutdowns in October to November 1961 and April to May 1962. Core physics tests include control rod bank calibrations, bank position at several temperature and xenon poison conditions vs core changes and energy release, shutdown neutron source decay and startup channel testing, and critical rod positions for stuck rod configurations. S… more
Date: July 1, 1962
Creator: Motte, F. G.; Best, W. C. & Kortheuer, J. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Radiation Leakage Survey of the Shield of the Nuclear Ship Savannah

Description: A detailed 4urvey of the radiation from the N.S. Savannah shield was made. The study was accomplished with the reactor at its full power of 69 Mw during a cruise of 2821 miles. The results of the detailed shield survey show that the design dose rate of 0.5 rem/yr for passenger spaces is not exceeded in any region to which passengers have access. ln the area restricted to crew access the design dose rate of 5.0 rem/yr is nowhere exceeded except in a small region on D'' deck in a room to which en… more
Date: August 29, 1962
Creator: Blizard, E.P.; Blosser, T.V. & Freestone, R.M. Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Calculation of Distance Factors for Power and Test Reactor Sites

Description: >Reference information and guidance on procedures and basic assumptions related to reactor siting are presented which can be used to calculate distance requirements consistent with current siting practices. A single method of competing distances and exposure for a general class of reactors is giveo. (J.R.D)
Date: January 1, 1962
Creator: DiNunno, J. J.; Anderson, F. D.; Baker, R. E. & Waterfield, R. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SNAP 7 Program--Task 8--Strontium-90 Fueled Thermoelectric Generator Development. Quarterly Progress Report No. 5, November 1, 1961 to January 31, 1962

Description: The SNAP 7A battery and converter were subjected to the required shock, vibration and temperature teats. The generator was fueled, postfueling radiation levels were checked and the generator was integrated into the complete SNAP 7A system. After the completion of acceptance tests, the SNAP 7A system was installed in a buoy which, in turn, was anchored in the bay where it will be subjected to further evaluation. The SNAP 7C generator was shipped for transport to Antarctica. The generator will po… more
Date: October 31, 1962
Creator: McDonald, W. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Theoretical Study of Destructive Nuclear Bursts in Fast Power Reactors

Description: The calculation of destructive nuclear bursts in fast reactors by an improved Bethe-Tait method, which, for purposes of calculation, neglects propagation of the pressure wave is described. TMen exact numerical calculations for hydrodynamic and neutronic conditions during the power burst are performed in order to assess the importance of this neglect. (auth)
Date: February 1, 1962
Creator: Jankus, V. Z.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A STUDY OF THE SHIELD OF THE UNIVERSITY OF ILLINOIS TRIGA MARK II RESEARCH REACTOR

Description: Detailed measurements were made of the fast-neutron and gamma dose rates and the thermal-neutron fluxes existing at the surfaces of the biological shield of the University of Illinois TRIGA Mark II Research Reactor. Dose rates and fluxes were found to be extremely low. A comparison was made by means of threshold foil techniques between the fast-neutron flux in a beam hole of the reactor during steady-state operation at 1 kw and during a nominal 250 Mw, 30 msec pulse produced by rapid insertion … more
Date: April 23, 1962
Creator: Blosser, T.V.; Freestone, R.M. Jr. & Miller, J.M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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HOT CELL DEMONSTRATION OF ZIRFLEX AND SULFEX PROCESSES. Report No. 3

Description: ABS>Hot cell demonstration of the Zirflex decladding process coupled with a modified Purex solvent extraction process was completed using specimens of Zircaloy-clad UO/sub 2/ irradiated to levels of 6150-14,600 Mwd/TU. Soluble losses of uranium and plutonium to the decladding solutions were about 0.05%. Centrifugation of the decladding solution is probably necessary to remove up to 1% of the UO/sub 2/ present as fines resulting from the fracture of low (93 to 95%) density pellets; high (96%) de… more
Date: May 14, 1962
Creator: Goode, J.H. & Baillie, M.G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Low Temperature Thermoluminescence of Gamma Irradiated Potassium Dihydrogen Phosphate

Description: Thermoluminescence in potassium dihydrogen phosphate (KDP) induced by Co/ sup 60/ gamma irradiation at liquid nitrogen temperature (-198 deg C) was investigated. Glow curves in the temperature range --196 to 0 deg C were measured for a series of gamma exposure dosages ranging from 10/sup 4/ roentgen to 5 x 10/sup 6/ roentgen. The heating rate used for glow curve measurements was 12 deg C per minute. Twice recrystallized Mallinckrodt reagent grade potassium dihydrogen phosphate, with a grain siz… more
Date: October 19, 1962
Creator: Sims, T. M.
Item Type: Refine your search to only Thesis or Dissertation
Partner: UNT Libraries Government Documents Department
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OGRE-P2, a Monte Carlo Program for Computing Gamma-Ray Leakage From Laminated Slabs With a Distributed Source

Description: A Monte Carlo program OGRE-P2 was written for the IBM-7090 to solve the problem of gamma radiation from a slab of laminated regions composed of various materials. The dose rate is calculated on one side of the slab. (J.R,D.)
Date: August 10, 1962
Creator: Trubey, D. K.; Penny, S. K. & Emmett, M. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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ULTRA HIGH TEMPERATURE REACTOR EXPERIMENT (UHTREX) HAZARD REPORT

Description: 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… more
Date: March 1, 1962
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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DEVELOPMENT OF PLUTONIUM-BEARING FUEL MATERIALS. Monthly Progress Letter for Month of February 1962

Description: 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
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Vapor Containment in the Oak Ridge Research Reactor

Description: Containment of the ORR is attained by means of a ventilation system which is capable of exhausting air from the building at a rate sufficient to ensure that all leakage of air at ground level is into the building. The exhaust air is treated by scrubbing and filtration and is discharged from a large stack at a height and velocity sufficient to guarantee that meteorological dispersion will reduce the resulting concentration of radioactive material to an acceptable level. Factors involved in selec… more
Date: August 23, 1962
Creator: Binford, F.T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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CRITICALITY EXCURSION OF NOVEMBER 10, 1961

Description: A criticality excursion occurred at the Oak Ridge Critical Experiments Laboratory on November l0, l961 as enriched uranium metal, neutron reflected and moderated by hydrogen, was being assembled. It is estimated that the energy yield was between 10/sup 15/ and 10/sup 16/ fissions. There was no personnel exposure or property damage. Fission product contamination, both airborne and contained in the metal, decayed sufficiently overnight to allow unhindered continuation of the experiment. The excur… more
Date: February 13, 1962
Creator: Callihan, D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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MARITIME REACTOR PROGRAM ANNUAL PROGRESS REPORT FOR PERIOD ENDING NOVEMBER 30, 1961

Description: Progress is reported on general support of the NS Savannah, operation of the pressurized-water in-pile loop, and advanced core development. A shield survey, iodine adsorption studies, a bioassay development program, preparation of replacement control rod drives, irradiation testing of pressure-vessel steel, a thermal insulation investigation, and an analysis of primary system components for gamm-emitting elements were carried out in the NS Savannah program. Water- chemistry studies in the press… more
Date: March 1, 1962
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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NASA-AEC LIQUID METALS CORROSION MEETING HELD DECEMBER 14-15, 1961, BROKHAVEN NATIONAL LABORATORY, UPTON, LONG ISLAND, NEW YORK

Description: Twenty-two papers are included. Separate abstracts were prepared for fifteen of these. The presentations not abstracted concern liquid metal research, evaluation of materials in gaseous and liquid Hg, liquid metal corrosion, of loop materials, effects of K vapor on refrsctory alloys, research program on Na components, Na loop studies, and determination of O in Na. (J.R.D.)
Date: October 31, 1962
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SNAP Radioisotope Space Programs Task 7. Quarterly Progress Report No. 7, April 1 Through June 30, 1961

Description: Safety analyses of the launch of SNAP-type units as to launch, ascent, and intermediate or final-stage failures are reported. A preliminary design study to define the configuration and performance of the Surveyor generator is completed. Dispersion patterns are found for radioactive materials released by the high-velocity vertical impact of Surveyor-type generators on the moon. High- velocity testing methods are discussed. Flare and telemetry capsules, designed to simulate fuel cores of nuclear … more
Date: October 31, 1962
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PERSONNEL-EXPOSURE AND CONTAMINATION CONTROL IN THE ROUTINE OPERATION OF THE ORNL RESEARCH REACTORS

Description: ABS>Measures are outlined that are taken to control occupational radiation exposure incurred in the routine operation of a reactor and in the conduct of activities associated with its operation. Those measures taken to minimize the frequency and effects of minor radiation and contamination incidents are also discussed. (C.H.)
Date: July 31, 1962
Creator: Sims, T.M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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POSSIBLE IMPLICATIONS OF THE DAMAGE BY RADIATION IN THE STORAGE OF PROPELLANTS IN OUTER SPACE AND TENTATIVE METHODS FOR ITS MEASUREMENT

Description: The damage by radiation that can be expected during the storage of H/sub 2/-bonded propellants in outer space is analyzed in terms of the available data on radiation levels. On this basis, the alternatives of storing the propellants as liquids or as solids, at low temperature, are discussed, and account is taken of recent results on their thermal behavior. Vitreous aggregation states of compounds that could crystallize spontaneously after long periods of irradiation are shown to present some ha… more
Date: July 1, 1962
Creator: McMillan, J.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Summary evaluation of potential liability from activities at Hanford

Description: This report investigates potential liability from activities at Hanford. The following topics are discussed: Contained inventory of radionuclides; Released inventory of radionuclides; Meteorological dispersion and deposition; Exposure criteria; Contamination areas; Economic factors; and Apportionment of damage costs in Canada.
Date: December 11, 1962
Creator: Watson, E. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Accidental nuclear excursion Recuplex operation 234-5 facility. Final report: Date of incident: April 7, 1962

Description: On Saturday morning, April 7, 1962, at about 1059 Armed Forces time, an accidental nuclear excursion occurred in the plutonium waste recovery facility (Recuplex) of the 234-5 Building. This excursion did not result in any mechanical damage or spread of contamination. Three employees of the General Electric Company received overexposures to gamma and neutron radiation. None were fatally exposed; in each case the overexposure was recognized promptly, and following medical observation and testing … more
Date: August 1, 1962
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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