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ORR Operations for Period April 1961 to April 1962
A summary of the activities in the 4th operational year is presented for the ORR. On-stream time at 30 Mw was relatively steady with 75.4 and 83.7% representing the lowest and highest quarters. Modification of the ball-latch mechanism of the shim-rod-drives is in progress. The primary cooling system bypass control valve was modified and a d-c pony motor was added at the No. 3 primary pump. This addition was made to increase the reliability of adequate water flow for afterheat cooling. A study of coreboiling detection is being conducted. (J.R.D.)
Date:
October 16, 1962
Creator:
Binford, F.T.; Casto, W.R. & Colomb, A.L.
Object Type:
Report
System:
The UNT Digital Library
ANNUAL REPORT ON PHYSICAL SCIENCES, ENGINEERING AND LIFE SCIENCES , JULY 1, 1961
The research program at Brooknaven is described. Current activities in physics, high-energy accelerators, instrumentation, chemistry, nuclear engineering, applied mathematics, biology, and medical research are outlined. (D.L.C.)
Date:
October 31, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
A SUMMARY OF INDUSTRIAL ACCIDENTS IN USAEC FACILITIES
The accident experience of the AEC contractor operation for 1959 and 1960 is reported. Incidents involving radio active materials are described. A table of inadvertent criticality was included to supplement other tables. A tabulation of exposure records at values from 0 to 15 r is given. (M.C.G.)
Date:
October 31, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
NUCLEAR SUPERHEAT PROJECT TENTH QUARTERLY PROGRESS REPORT, OCTOBER-DECEMBER 1961
Results in the Nuclear Superheat Project are summarized. Topics covered include: conceptual design and program evaluation, fuel technology, materials development, experimental physics, coolant chemistry, heat transfer, mechanical development, SADE and E-SADE, and mixed spectrum superheat study. (M.C.G.)
Date:
October 31, 1962
Creator:
Pennington, R.T.
Object Type:
Report
System:
The UNT Digital Library
EXPERIMENTAL INVESTIGATION OF THE EFFECTS OF ULTRASONIC VIBRATIONS ON BURNOUT HEAT FLUX WITH BOILING WATER. Quarterly Technical Progress Report No. 3, April-June 1961
The heat-transfer loop was completed and is in operation. Difficulty was experienced in obtaining a sufficiently strong connection between the burnout- detector voltage tap and the heating element. This problem and its potential solution are described. The lack of means of obtaining controlled burnout prevented collection of data on the burnout effects of the ultrasonic field. (auth)
Date:
October 31, 1962
Creator:
Romie, F.E.
Object Type:
Report
System:
The UNT Digital Library
CHEMICAL ENGINEERING DIVISION SUMMARY REPORT, JULY, AUGUST, SEPTEMBER, 1961
Development activities are reported on pyrometallurgical processes including melt refining and those using liquid metal solvents. Development of processing facilities for EBR II is also reported. In other work, laboratory- and engineering-scale investigations on fluoride volatility processes were condueted, and conversion of UF/sub 6/ to UO/sub 2/ was studied. Investigations are also reported concerning the kinetics of metal ignition and oxidation, and metalwater reactions. In work associated with reactor chemistry, data on nuclear constants are reported and developments in thermoelectricity and reactor decontamination are described. (J.R.D.)
Date:
October 31, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
CORE A CRITICAL STUDIES FOR THE ENRICO FERMI ATOMIC POWER PLANT ON ZPR-III
A critical studies program for the Enrico Fermi Atomic Power Plant was run with the ZPR-III fast critical facility. The objectives of this program included determination of the U enrichment required for criticality, the effect of minor variations in core and blanket composition, reactivity coefficients, control and safety rod characteristics, power distribution, spectral indices, and the reactivity worth and wave shape of the oscillator rod. The experimental program was separated into two phases. The first phase involved investigatlona of a clean assembly, which was a simplified and homogenized core and blanket geometry constructed for ease of experimental manipulation and analysis. The second phase involved experiments on the engineered, or as-designed, core. This assembly included such engineering details as control and safety rod channels, core end gaps, and a precise reconstruction of the core outline. This provided detailed information on worths of control rods and fuel subassemblies, power distribution, and the effect of variations in core and end-gap dimensions. The application of critical experiment data to the determination of the Enrico Fermi reactor characteristics has established the U/sup 235/ enrichment for the fuel alloy, worths of fuel subassemblies, and the B/sup 10/ enrichment for the control and safety rods. In addition, …
Date:
October 1, 1962
Creator:
Branyan, C.E.
Object Type:
Report
System:
The UNT Digital Library
SNAP Radioisotope Space Programs Quarterly Progress Report No. 9, October 1 Through December 31, 1961
All Phase I and Phase II testing was completed. Both launches of Phase I were successful, neither Phase II launches were successful. Test data recovered on Phase I launchings included optical coverage of re-entry and the trajectory and weather data; no telemetry canister temperature data were obtained. No test data were obtained on Phase II experiments. Reduction of Phase I test data was begun. The Phase II (Sub-subtask 7.3.2) was terminated December 20, 1961, when no test data were recovered for comparison with the analytically predicted results. The Sub-subtask 7.3.3 program (Generator Re-entry Burnup Study) was completed and terminated December 29, 1961. The study objectives were met. The Sub-subtask 7.3.4 program (High Altitude Sampling) was terminated when it was completed November 30, 1961. All study objectives were met. Topical reports were prepared on Sub-subtasks on the work performed in the reporting period that was not included in the topical reports is included. Checkout and troubleshooting operations on the last two subroutines and main radioisotope shielding code were completed. Results from several runs of a simple check problem compared well with published data. (auth)
Date:
October 31, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
RADIOISOTOPE AND RADIATION APPLICATIONS. Quarterly Progress Report
The study of the mechanism of free-radical formation and decay in polymeric materials was continued and extended to include an investigation of the potential application of this information to the development of novel graft copolymers. The study of postirradiation grafting techniques employing both peroxide initiation and direct grafting was continued. In addition, the effect of molecular weight on site formation was further investigated. Licenses and license applications for approximately 300 by-product material licenses were reviewed to obtain information on environmental conditions of source usage. The feasibility of testing sealed-source response to normal environments by accelerated test procedures was studied. Indications are that the approach will probably not be applicable to either vibration or abrasion stresses but may be for corrosion stresses. (auth)
Date:
October 18, 1962
Creator:
Sunderman, D.N., ed.
Object Type:
Report
System:
The UNT Digital Library
Evaluation of Subsize Izod Specimen Designs for Determining the Notch Toughness of Zircaloy-2
Correlations were made on Zircaloy-2 Izod impact data and Charpy-V drop- weight data. Subsize Izod impact specimens of various geometries and notch configurations and standard ASTM Charpy-V specimens were prepared from bar and plate stock and tested. Drop-weight tests were also conducted and the NDT (nil- ductility transition) temperature was determined for 1/2 in. Zircaloy-2 plate. Results show that the impact properties of Zircaloy-2 are sensitive to hydrogen concentration, specimen and notch geometry, and specimen and notch orientation. No subsize specimen design was found which yielded impact curves similar to those obtained with standard Charpy-V notch specimens, but designs suitable for in- pile testing were found. It was found that Zircaloy-2 has the property of arresting a moving crack even at temperatures of --100 deg C and lower. (P.C.H.)
Date:
October 1, 1962
Creator:
Prislinger, J. J.
Object Type:
Report
System:
The UNT Digital Library
Delayed Failure Hydrogen Embrittlement of Zirconium. Summary Report, September 15, 1961 to September 14, 1962
The extent to which zirconium and zirconium alloys exhibit delayed failure (static fatigue) as caused by a combination of absorbed hydrogen and applied stress was investigated. Susceptibility to time-dependent fracture was evaluated for unalloyed zirconium and Zircaloy-2 with 200 and 500 ppm hydrogen as well as for an experimental Zr Al-Sn-Mo alloy and the Canadian Zr-2.5Nb cladding material. For unalloyed zirconium and Zircaloy-2 containing up to 500 ppm hydrogen, no room-temperature, timedependent fracture occurred which could be definitely attributed to the delayed failure phenomenon; an increased grain size, 20% cold deformation by rolling, or corrosion in 750 deg F steam did not significantly affect this behavior. The curve of applied stress versus time to failure at room temperature for the high-strength Zr-Al-Sn--Mo alloy containing 500 ppm hydrcgen established a strong susceptibility to delayed failure due to hydrogen absorption; studies on vacuum-annealed material showed no failures. Further, reduced temperature indicated that the occurrence of static fatigue is temperature dependent. Data for heattreated Zr 2.5Nb containing 500 ppm hydrogen indicated that this material is moderately sensitive to delayed failure at room temperature; higher hydrogen contents caused a greatly increased susceptibility to time-dependent fracture. (auth)
Date:
October 10, 1962
Creator:
Weinstein, D. & Holtz, F. C.
Object Type:
Report
System:
The UNT Digital Library
GAUGE FOR MEASURING BOW OF TUBES
A mechanical gage was designed to measure the bow over any one-foot length of long cylindrical material. The gage was used successfully for measuring bow in components of tubular fuel elements at the Savannah River Laboratory. (auth)
Date:
October 31, 1962
Creator:
Alewine, G.B.
Object Type:
Report
System:
The UNT Digital Library
AN IBM 7090 FORTRAN PROGRAM FOR ASME UNFIRED PRESSURE VESSEL DESIGN AND PRELIMINARY COST ESTIMATION
An IBM 7090 FORTRAN program was written for the preliminary design and cost estimation of unfired pressure vessels with or without a jacket. Both vessel and jacket designs conform to the 1959 ASME Boiler and Pressure Vessel Code, Section VIII, Unfired Pressure Vessels. Vessels and jackets from 5 in. pipe through 84 in. o.d. and 1/4 in. through 1 1/2 in. in metal thickness may be designed by this program as written. Total vessel cost is the sum of metal and fabrication costs, each on a weight basis. (auth)
Date:
October 17, 1962
Creator:
Prince, C. E. & Milford, R. P.
Object Type:
Report
System:
The UNT Digital Library
Thermal-Stress and Strain-Fatigue Analyses of the MSRE Fuel and Coolant Pump Tanks
Thermal-stress and strain-fatigue analyses of the MSRE fuel and coolant pump tanks were completed for determining the quantity of coollng air required to obtain the maximum life of the pump tanks and to determine the acceptability of the pump tanks for the intended service of 100 heating cycles from room temperature to 1200 deg F and 500 reactor power-change cycles from zero to 10 Mw. A cooling-air flow rate of 200 cfm for the fuel pump tank was found to be an optimum value that provided an ample margin of safety. The coolant pump tank was found to be capable of the required service without air cooling. (auth)
Date:
October 1, 1962
Creator:
Gabbard, C.G.
Object Type:
Report
System:
The UNT Digital Library
SNAP 7 Program--Task 8--Strontium-90 Fueled Thermoelectric Generator Development. Quarterly Progress Report No. 5, November 1, 1961 to January 31, 1962
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 power a five-watt U. S. Navy remote weather station. Tests were also conducted to determine the operational characteristics of SNAP 7B and 7D thermoelectric couples. Also, the reliability model of the generator was operated at high temperature for 23 days. The electrical, converter and battery specifications for the SNAP 7D system were completed and released. The primary effort in the fael processing phase of the program was to provide the necessary liaison with the personnel installing the processing equipment. Maintenance and checkout guides were written to assure satisfactory installation and continued performance throughout the fuel processing span. An operation procedure guide was written to describe the engineering concept of the fuel processing operation. The guide was written for the personnel …
Date:
October 31, 1962
Creator:
McDonald, W. A.
Object Type:
Report
System:
The UNT Digital Library
SNAP Programs: Task 6--Fuel Technology Development Program. Quarterly Progress Report No. 7, April 1 Through June 30, 1961
Progress made in the development of isotope power sources for thermoelectric and thermionic conversion to electrical energy is reported. The Heavy Elements Processing Facility for processing americium and fabricating americium capsules for irradiation was opened and hot operation was begun. Modifications to the americium purification system were completed and checkout operations were begun. Process specifications were established for dissolution of the irradiated capsules and the major equipment for this operation was designed. Experimental work on the purification of curium was continued. Blending and crushing studles were conducted to establish techniques and procedures for preparing curium carbide and for producing homogeneous cermet fuel forms. Investigations were also made into the compatibility of various matrix and container materials with curium carbides and oxides. Flow diagrams for the fuel form and isotope encapsulation processes were completed. A safety analysis was conducted which verified the integrity of the americium capsules during all stages of the irradiation program. (auth)
Date:
October 31, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
DEVELOPMENT OF PLUTONIUM-BEARING FUEL MATERIALS. Progress Report, October 1-December 31, 1961
Continued effort is reported on preparation and characterization of PuO/ sub 2/ and UO/sub 2/-- PuO/sub 2/ mixtures. Sintering and characterization of pellets for irradiation tests was emphasized, and efforts were also devoted to plasma torch production of spherical PuO /sub 2/ and coating of oxide materials. PuO/sub 2/ produced by the oxalate process from low concentration feed contains agglomerates which are not readily broken down, while that produced from normal feed contains larger agglomerates which are easily dispersed ultrasonically, and are more easily calcined. The water filtration method for determining total porosity of powders was adapted for use with PuO/sub 2/. Moisture pickup studies show that the problems encountered with PuO/sub 2/ are similar to those found in handling ceramic-grade UO/. Reproducibility tests carried out on UO/sub 2/--PuO/ sub 2/ mixtures indicate that production methods are satisfactory. Lab-scale experiments on production of PuO/sub 2/-- UO/sub 2/feed for the plasma torch indicate that further work is worthwhile. Adaptation of a potentiometric filtration for Pu is reported. A twophase microstructure found in PuO/ after sintering in N6% H atmosphere was identified as PuO/sub 2/ and cubic Pu/sub 2/O/ sub 3/. Spherical particles were produced in the plasma torch using crushed or …
Date:
October 31, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
DEVELOPMENT OF PLUTONIUM-BEARING FUEL MATERIALS. Progress Report for Period January 1 through March 31, 1962
During this reporting period, particular effort was of aced on powder blending and pellet sintering studies prior to irradiation sample fabrication, and, subsequently, the production and characterization of the pellets slated for irradiation. Also, PuO/sub 2/ and UO/sub 2/-PuO/sub 2/ characterization studies were continued, and new techniques are being developed. Specifically, dynamic moisture pickup determinations on PuO/sub 2/ were made in moist air, N, and CO/ sub 2/ atmospheres using a recording thermogravimetric balance; the Sharples Micromerograph was committed to Pu, and powder particle size distributions were measured and compared with previous determinations made with air-permeability equipment; and the suitability and reliability of analytical chemistry assaying procedures such as x-ray-fluorescence and gamma spectrometry are being evaluated. Prototype work on UO/sub 2/ for the direct precipitation of PuO/sub 2/ and PuO/ sub 2/-UO/sub 2/ feed materials for swaging, vibratory compaction, and dispersion fabrication was also continued. In addition, investigation of PuO/sub 2/ spherical particle formation by mechanical buildup and by plasma torch fusion was extended. Associated reactor physics studies were concentrated on the further comparison of Pu and U/sup 235/ in near-thermal converter reactors. In preparation for the fabrication of irradiation test specimens to be prepared by the mechanical blending of …
Date:
October 31, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Chemical Processing Technology Quarterly Progress Report, January-March 1961
Studies are reported on aqueous zirconium processing, dissolution of BeO- UO/sub 2/ ceramic fuel, the aqueous stainless steel process, the behavior of dibutyl phosphates, use of boron (boric acid) solution to assure critical safety, fluidized bed calcination, conversion of amorphous alumina to alpha alumina, the Demonstrational Waste Calcining Facility, removal of long-lived radioisotopes from waste solutions, separation of iron, nickel, and chromiun from stainless steel waste solutions, electrolytic dissolution, effects of stray currents, electrolytic disintegration of Zircaloy-2, corrosion evaluation of materials of construction, the ARCO process, a direct air pulsed extraction column, and large vessel criticality control. (M.C.G.)
Date:
October 31, 1962
Creator:
Bower, J. R.
Object Type:
Report
System:
The UNT Digital Library
Physics Division Summary Report, February-March 1962
Progress is reported in experimental nuclear physics on calculations concerning the distribution of lifetimes of neutrons in glass scintillation neutron detectors and on the probabilities for single, double, and triple scattering of neutrons in thin plates. Precision measurements of gamma-ray energies and intensities were used to modify and extend the level scheme of Hf/ sup 178/. The presence of three K = 0 rotational bands (besides the ground state) and two K = 2 rotational bands are indicated in the level scheme of this isotope. In other work the fluorescence properties of polystyrene were found to depend on concentration of residual styrene monomer and the average molecular weight. Research is also reported in theoretical physics on dynamics of nuclear collective motion, scatter ing of alpha particles by a vibrational nucleus, flux quantization and time-reversal degeneracy, and elastic nucleonnucleon scattering at high energies and small angles. (J.R.D.)
Date:
October 31, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Low Temperature Thermoluminescence of Gamma Irradiated Potassium Dihydrogen Phosphate
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 size between 100 and 170 mesh, was used for most samples. In the case of the powder samples, the glow curve for an exposure dose of 10/sup 4/ roentgen exhibited two peaks in this temperature range, one at approximately --78 deg C and the other at approximately -146 deg C. The -78 deg C peak split into two distinct peaks with increasing dosage. At still higher doses an additional peak at about -9 deg C became evident. This peak may, however, be due to aluminum oxide. Calculation of the trap depth, E, and the frequency factor, s, associated with the --78 deg C peak, by the approximate method of Grossweiner yielded values of 0.485 ev and 9.97 x 10/sup 10/ sec/sup -1/ …
Date:
October 19, 1962
Creator:
Sims, T. M.
Object Type:
Thesis or Dissertation
System:
The UNT Digital Library
Physics Division Summary Report, April-May 1962
None
Date:
October 31, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
EXPERIMENTAL INVESTIGATION OF THE EFFECTS OF ULTRASONIC VIBRATIONS ON BURNOUT HEAT FLUX WITH BOILING WATER. Quarterly Technical Progress Report, October-December 1960
>The effects of an ultrasonic field on the maximum nucleate heat flux that can be sustained by boiling water in a flow system are being investigated. Design and procurement of apparatus is underway. (M.C.G.)
Date:
October 31, 1962
Creator:
Romie, F.E.
Object Type:
Report
System:
The UNT Digital Library
IDAHO DIVISION SUMMARY REPORT, APRIL THROUGH SEPTEMBER 1961
Research and development progress is reported on TREAT, BORAX V, ZPR- III, EBR-II, and the reactor operations personnel training program. (M.C.G.)
Date:
October 31, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library