Aerodynamic Re-Entry Analysis. Task 2. Thermoelectric Generator Summary Report (open access)

Aerodynamic Re-Entry Analysis. Task 2. Thermoelectric Generator Summary Report

An analytical trajectory and aerothermodynamic analysis of a satellite containing a Task 2 thermoelectric generator was completed. A 300-statute mile circular polar orbit was used for this analysis and the launch was assumed to be from Vandenberg Air Force Base. Results of this study show that upon natural decay from a successful mission, the radio-cerium fuel will burn up in space at high altitude, thus only a very minor amount of radio cerium will be released to the stratosphere. A complete analyses of the fate of the radio-cerium fuel following various aborted launching attempts also was carried out. Charts summarizing the various assumed failures and locations of the fuel following failure are shown. A technical discussion of the methods used in performing the analysis is included in the report. (auth)
Date: December 27, 1960
Creator: Oehrli, R.
System: The UNT Digital Library
Basis for design scope: Plutonium Reclamation Facility, Z Plant, Project CAC-880 (open access)

Basis for design scope: Plutonium Reclamation Facility, Z Plant, Project CAC-880

This report discuss the design of the Plutonium Reclamation Facility the capacity of which will be 300 kilograms per month or 3600 kilograms per year or plutonium. The subject facility, as the name implies, must be extremely flexible in its ability to handle a wide variety of feed materials. The new facility will be operating on a three-shift day, five-day week, 40-week year with an overall efficiency of 75 percent; twelve weeks per year will be required for ``turnaround`` time to enable campaign operation for segregation of feed plutonium by isotopic content.
Date: April 27, 1960
Creator: Braden, D. E.
System: The UNT Digital Library
Goal exposure for central zone block discharge at DR reactor (open access)

Goal exposure for central zone block discharge at DR reactor

None
Date: April 27, 1960
Creator: Shimer, R. D.
System: The UNT Digital Library
Attenuation effectiveness of the Hanford reactor iron masonite shields (open access)

Attenuation effectiveness of the Hanford reactor iron masonite shields

None
Date: April 27, 1960
Creator: Smalley, W. L.
System: The UNT Digital Library
Quarterly Health Physics Report. Through March 31, 1960 (Deleted Version) (open access)

Quarterly Health Physics Report. Through March 31, 1960 (Deleted Version)

A resume of Health Physics activities for January, February, and March, 1960 is presented. Discussions and tabulations which summarize results of field surveys, bioassay, personnel monitoring, and environmental surveys are included.
Date: May 27, 1960
Creator: Meyer, H.E.
System: The UNT Digital Library
Densities of Ammonium Fluoride-Ammonium Nitrate-Ammonium Hexafluozirconate Solutions (open access)

Densities of Ammonium Fluoride-Ammonium Nitrate-Ammonium Hexafluozirconate Solutions

The densities of various Zirflex-type solutions at 25 gas-cooled C can be expressed by the equation: p calc = (0.99710 + 0.03l57 m) + (0.02046 - 0.002659 m)c -(0.0033460.000703 m)c3/2 + 0.14349x + 0.49z where m = moles liter/ sup -1/ NH/sub 4/NO/sub 3/, c = moles liter/sup -1/ NH/sub 4/F, x = moles liter/ sup -1/ (NH/sub 4/)/sub 2/ZrF/sub 6/, and z = moles liter/sup -1/ UO/sub 2/(NO/ sub 3/)/sub 2/. This eq uation fits the data with a sigma value of 0.00018 g/ml for NH/sub 4/FNH/sub 4/NO/sub 3/ solutions, 0.00024 g/ml for NH/sub 4/F-(NH/sub 4/ )/sub 2/ZrF/sub 6/ solutions, and 0.0002 g/ml for solutions containing UO/sub 2/ (NO/sub 3/)/sub 2/ and/or NH/sub 4/F-NH/sub 4/NO/sub 3/ over the range of 0.0M to 6.0M NH/sub 4/F, 0.0M to 1.6M NH/sub 4/NO/sub 3/, 0.0M to 0.5M (NH/sub 4/)/sub 2/ ZrF/sub 6/, and 0.0M to 0.0025M UO/sub 2/(NO/sub 3/)/sub 2/. (auth)
Date: October 27, 1960
Creator: Teague, J. L. & Pearson, D. P.
System: The UNT Digital Library
DISPERSION STRENGTHENING OF IRON-ALUMINUM BASE ALLOYS: A FEASIBILITY STUDY (open access)

DISPERSION STRENGTHENING OF IRON-ALUMINUM BASE ALLOYS: A FEASIBILITY STUDY

The feasibility of improving the mechanical properties at 1700 to 1800 deg F of oxidation-resistant Fe-Al-Cr alloys by means of a refractory dispersion was explored. A literature search was conducted, preliminary experimental determinations of properties of the alloy and its oxides were carried out, and certain mathematical relations between dispersion charaeteristics and metallurgical variables were derived. The results indicate that the alloys can be strengthened sufficiently by using a dispersion with an interparticle spacing of about 2 to 3 mu . High-temperature native oxides of the Fe-Al-Cr alloy consist largely of Al/sub 2/O/sub 3/ and in theory would serve as a aatisfactory second phase. (auth)
Date: December 27, 1960
Creator: King, B.
System: The UNT Digital Library
SRE STANDARD OPERATING PROCEDURES (open access)

SRE STANDARD OPERATING PROCEDURES

General SRE operating instructions, limits, and procedures are listed. Specific operating instructions are given for the reactor, sodium heat-transfer systems, sodium service systems, service cooling system, helium system, nitrogen and dehumidification systems, vent system, liquid waste system, fuel handling machine, building ventilation systems, wash cells, emergency power system, pump coolant systems, crane operation, off-normal conditions, and special procedures. (W.D.M.)
Date: June 27, 1960
Creator: Durand, R.E.; Jenkins, O.G.; Johnson, L.L.; Pearson, E.N. & Vorderbrueggen, L.E.
System: The UNT Digital Library
Chemical Technology Division, Unit Operations Section Monthly Progress Report, July 1960 (open access)

Chemical Technology Division, Unit Operations Section Monthly Progress Report, July 1960

A critical review of the literature revealed no experiments on uranyl ion transfer from an aqueous to a tributyl phosphate phase which positively measured the kinetics of the chemical reaction at the interphase. Drawing isorhythmic lines on a three component diagram gives a complex correlation for the compaction of three sizes of glass beads. Neither the use of thoria sols nor high feed solution concentrations of thorium nitrate gave any significant increase in mean particle diameters over those obtained from nitrate solutions of lower concentrations in flame denitration. A hydraulic film resistance has been detected in the anion exchange of uranyl sulfate into Dowex 2lK, and chloride elution was found to give a higher apparent uranium diffusion coefficient than nitrate elution. The rate of dissolution of mixed thorium-uranium oxides was determined as a function of the per cent of mixed oxides dissolved. Mixing in tanks packed with boron glass Raschig rings is being continued. The SRE hydraulic dejacketer has been operated successfully with prototype fuel rods. Excessive foaming was encountered when sheared stainless-clad UO/sub 2/ was suddenly contacted with boiling 13 M nitric acid. While attempting to shear a prototype Yankee subassembly with Kanigan brazed diffusion bonded joints, a five …
Date: October 27, 1960
Creator: Whatley, M E; Haas, P A; Horton, R W; Ryon, A D; Suddath, J C & Watson, C D
System: The UNT Digital Library
Final Report on the Pinot Experiment (open access)

Final Report on the Pinot Experiment

The Pinot Project was designed to provide some indication of the extent to which gases from a confined underground explosion in oil shale would migrate parallel to the bedding planes. At 0800 on Aug. 2, 1960, 946 lb of nitromethane was fired in shot hole No. 1. There was no visible damage to the mine adit or to any structure associated with cation of the extent to which gases from a confined underground explosion in oil shale would migrate parallel to the bedding planes. At 0800 on Aug. 2, 1960, 946 lb of nitromethane was fired in shot hole No. 1. There was no visible damage to the mine adit or to any stnucture associated with the workings. Gas samples collected from sampling holes near the shot hole were analyzed for Kr/sup 85/, which had been included with the nitromethane as a tracer. It appeared that the Kr/sup 85/ concentration in the samples out to 50 ft was more or less independent of space and time between +2 and +50 hr. Relativsly little Kr/sup 85/ was detected at 125 ft and none beyond. About (20 plus or minus 10)% of the Kr/sup 85/ escaped into ths adit. The results of …
Date: December 27, 1960
Creator: Adelman, F. L.; Bacigalupi, C. M. & Momyer, F. F.
System: The UNT Digital Library
Refueling-Core 1, Seed 1 Radiation Survey of Scram Shaft Assemblies. Test Results T-643704 (open access)

Refueling-Core 1, Seed 1 Radiation Survey of Scram Shaft Assemblies. Test Results T-643704

A test was conducted to determine the radiation level of several scram shaft assemblies after their removal from the reactor vessel during Core 1 Seed 1 refueling. Data on radiation levels near the assemblies 75 days after shutdown are given. (J.R.D.)
Date: July 27, 1960
Creator: unknown
System: The UNT Digital Library
Magnetic Recorder for Nuclear Pulse Application. Final Report Covering Period: June 5, 1959 to June 5, 1960 (open access)

Magnetic Recorder for Nuclear Pulse Application. Final Report Covering Period: June 5, 1959 to June 5, 1960

An analog recording technique was investigated in which pulses from a scintillation counter are stretched to a width compatible with the bandwidth of the recorder. Three types of playback systems were considered, i.e., unequalized velocity, equalized velocity, and flux sensitive playback. The results of the three systems were found to be comparable. Loss in resolution in the process was primarily due to nonuniformities in magnetic tape properties and maintenance of an adequate head to tape contact. Instrumental line widths of the order of 3% were achieved using equipment of moderate cost. (For preceding period see ARF- 1151-5.) (auth)
Date: June 27, 1960
Creator: Burgwald, G.M. & Stone, C.A.
System: The UNT Digital Library
A Survey Report on Lithium Hydride (open access)

A Survey Report on Lithium Hydride

ABS>The physical and chemical properties of lithium hydride are described, based on reasonably full coverage of the available unclassified literature as of July 1, 1960. Where possible, the data are presented critically. Lithium deuteride and lithium hydride gases are included. Practical matters such as thermal stability, corrosive character, utilization, handling, fabrication, and analysis are discussed. This report replaces report NYO-3957 and its supplement NYO-8022. 230 references. (auth)
Date: October 27, 1960
Creator: Messer, C.E.
System: The UNT Digital Library
Effective Cadmium Cutoff Energies. Supplement (open access)

Effective Cadmium Cutoff Energies. Supplement

Cutoff energies were calculated for height/diameter (H/D) values of 1, 3, 6, and 11.25 for cadmium cylinders. These are presented along with the values for H/D = 2 for comparison. Similar values for boron filters for H/D values of 1 and 2 are shown. (M.C.G.)
Date: May 27, 1960
Creator: Stoughton, R. W.; Halperin, J. & Lietzke, M. P.
System: The UNT Digital Library