HRT-CP INSTRUMENTATION DESIGN MANUAL (open access)

HRT-CP INSTRUMENTATION DESIGN MANUAL

The installation and design of the HRT-Core Processing Plant are described in detail so that operation and maintenance of the plant may be made more effective. Process instruments will be described fully, but auxiliary instrumentation such as pressure gauges, rotameters, etc. will not be mentioned. Where detailed questions arise as to electrical circuitry or instrument connections, the drawings and specification sheets should be consulted. (auth)
Date: August 17, 1956
Creator: Adams, R.K.
Object Type: Report
System: The UNT Digital Library
Request for irradiation, request for examination and evaluation of new, improved fuel elements in ETR facilities. Extension of GEH-10 (open access)

Request for irradiation, request for examination and evaluation of new, improved fuel elements in ETR facilities. Extension of GEH-10

None
Date: September 17, 1959
Creator: Albaugh, F. W.
Object Type: Report
System: The UNT Digital Library
Estimates of Temperature Rise and Pressure Drop Effects of Sample Holder in the HRT Core (open access)

Estimates of Temperature Rise and Pressure Drop Effects of Sample Holder in the HRT Core

None
Date: July 17, 1956
Creator: Aven, R. E.
Object Type: Report
System: The UNT Digital Library
Irradiation Experiment on Aluminum Fuel Plates Containing a 48 Wt. % Uranium-3 Wt. % Silicon-49 Wt. % Aluminum Alloy with 20% Enrichment in the U-235 Isotope (open access)
Semi-Monthly Progress Report on ETR Development, Covering Work During Period from April 1 to April 16 (open access)

Semi-Monthly Progress Report on ETR Development, Covering Work During Period from April 1 to April 16

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Date: April 17, 1956
Creator: Beaver, R. J.
Object Type: Report
System: The UNT Digital Library
100 Areas weekly report, February 17, 1955 (open access)

100 Areas weekly report, February 17, 1955

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Date: February 17, 1955
Creator: Bellas, H. W.
Object Type: Report
System: The UNT Digital Library
Service of reduction bombs plutonium purification and fabrication 234-5 Building (open access)

Service of reduction bombs plutonium purification and fabrication 234-5 Building

None
Date: April 17, 1952
Creator: Benoliel, R.W.
Object Type: Report
System: The UNT Digital Library
REACTOR ENGINEERING DIVISION QUARTERLY REPORT FOR DECEMBER 1, 1949 THROUGH FEBRUARY 28, 1950 (open access)

REACTOR ENGINEERING DIVISION QUARTERLY REPORT FOR DECEMBER 1, 1949 THROUGH FEBRUARY 28, 1950

None
Date: March 17, 1950
Creator: Bigler, W. P.
Object Type: Report
System: The UNT Digital Library
Preliminary Report on the Results of the Oak Ridge Research Reactor Hydraulic Test (open access)

Preliminary Report on the Results of the Oak Ridge Research Reactor Hydraulic Test

The results of tests to determine the actual coolant flow through various core channels in the Oak Ridge Research Reactor are plotted, tabulated, and discussed. (M.H.R.)
Date: February 17, 1958
Creator: Binford, F.T.
Object Type: Report
System: The UNT Digital Library
Status report for chemical development, sections A and B for week ending August 10, 1956 (open access)

Status report for chemical development, sections A and B for week ending August 10, 1956

None
Date: August 17, 1956
Creator: Blanco, R. E. & Ferguson, D. E.
Object Type: Report
System: The UNT Digital Library
POWER DISTRIBUTION OF TOWER SHIELDING FACILITY REACTOR (TSR) (open access)

POWER DISTRIBUTION OF TOWER SHIELDING FACILITY REACTOR (TSR)

The horizontal and vertical power distribution for a 5 x 7 fuel element loading of the TSR is presented. (auth)
Date: January 17, 1957
Creator: Blessing, W.G.
Object Type: Report
System: The UNT Digital Library
300-M Area weekly report, November 11--17, 1955, Savannah River Plant (open access)

300-M Area weekly report, November 11--17, 1955, Savannah River Plant

None
Date: November 17, 1955
Creator: Bloomsburg, M. S.
Object Type: Report
System: The UNT Digital Library
PRELIMINARY ANALYSIS OF SUPERCHARGED NUCLEAR RAMJET PROPULSION SYSTEM (open access)

PRELIMINARY ANALYSIS OF SUPERCHARGED NUCLEAR RAMJET PROPULSION SYSTEM

A preliminary analysis has been made to compare the performance.of a ceramic ramjet reactor powerplant, such as described in General Electric Report No. XDC-56-5-81, with that of such a powerplant supercharged by a metallic-vapor-cycle compressor jet. Performance at sea level, Mach 2.5 is ·reported for the vapor-cycle compressor jet alone, for the ramjet alone, and for the compressor jet - ramjet combination. Results indicate that adding the compressor-jet as a supercharger for the ramjet provides an increase in specific thrust of about 20 percent over that of the ramjet alone, with an attendant increase in thermal efficiency of about 20 percent over that of the ramjet alone.
Date: May 17, 1957
Creator: Boppart, J. A.
Object Type: Report
System: The UNT Digital Library
Abrasive Cutting of Irradiated Uranium (open access)

Abrasive Cutting of Irradiated Uranium

None
Date: September 17, 1953
Creator: Boyd, C. L.
Object Type: Report
System: The UNT Digital Library
Health-Physics Monthly Information Report. October 1-31, 1950. (open access)

Health-Physics Monthly Information Report. October 1-31, 1950.

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Date: November 17, 1950
Creator: Bradley, J. E.
Object Type: Report
System: The UNT Digital Library
Zirconium-95 as a Fission Monitor (open access)

Zirconium-95 as a Fission Monitor

None
Date: July 17, 1956
Creator: Brooksbank, W. A., Jr.
Object Type: Report
System: The UNT Digital Library
Final reports on PT 105-551-A and Supplement A, ``High exposure thorium`` and PT 105-516-A, ``Effects of irradiation of thorium slugs`` (open access)

Final reports on PT 105-551-A and Supplement A, ``High exposure thorium`` and PT 105-516-A, ``Effects of irradiation of thorium slugs``

This report discusses Production Test 105-516-A which was written to determine the stability by both measurement and visual examination, of thorium slugs as used in flattening columns to exposures in excess of 400 MWD/AT. Both rolled and extruded thorium slugs were used; the highest exposures reached were about 1000 MWD/AT. Also discussed is Production Test 105-551-A which was written to demonstrate the stability of thorium slugs as used in flattening columns at exposures up to approximately 1500 MWD/AT; the supplement authorized exposures up to 3000 MWD/At. Six tubes of 10-66 material already in the pile were chosen; these have been discharged at exposures varying from {approximately}1230 to {approximately}2000 MWD/At.
Date: November 17, 1954
Creator: Brugge, R. O.
Object Type: Report
System: The UNT Digital Library
OXIDATION OF PLUTONIUM (III) BY SODIUM NITRITE (open access)

OXIDATION OF PLUTONIUM (III) BY SODIUM NITRITE

The reaction velocity constant for the oxidation of Pu(III) by nitrite in HNO/sub 3/ solution containing ferrous sulfanate is given. The reaction rate was found to be measurable by means of spectrophotometry. The data indicate the reaction to be a pseudo first-order reaction in the region of HNO/sub 3/ and nitrite concentration of interest. The reaction velocity constant, expressed as a first-order reaction with respect to Pu, was found for several values of HNO/ sub 3/ and nitrite concentrations. The HNC/sub 3/ reaction velocity constant relationship is given. The oxidation of the ferrous sulfamate--Pu(III Pu(III) solution proceeds successively through the sulfamate, ferrous, and Pu(III) ions. An autocatalytic mechanism is asscciated with the oxidation of both ferrous and Pu ions which obviates the possibility of simple calculations of constants based on nitrite concentration. An empirical relationship between the reaction velociiy constant and the (added) nitrite concentration is given. (auth)
Date: July 17, 1957
Creator: Brunstad, A.
Object Type: Report
System: The UNT Digital Library
Procedures for Testing Fission Product Adsorbers HRT Engineering Test Procedure IIA, 10a, b, c, d (open access)

Procedures for Testing Fission Product Adsorbers HRT Engineering Test Procedure IIA, 10a, b, c, d

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Date: April 17, 1956
Creator: Burch, W. D.
Object Type: Report
System: The UNT Digital Library
Status and Future Program of Homogeneous Reactor Fuel Processing Studies (open access)

Status and Future Program of Homogeneous Reactor Fuel Processing Studies

The behavior of insoluble corrosion products in the HRT is generally understood and studies of the removal of these solids by hydroclones can logically be terminated after the effect of higher processing rates by the multiple hydroclone has been determined. Chemical descaling may be required to supplement solids removal by hydroclones. Laboratory studies to find suitable reagents will be continued in conjunction with decontamination work presently in progress. Rare earth solubility levels and thus poison fraction from this group will be measured after the addition of signiflcant quantities of four important elements has minimized analytical detection problems. The role of the tellurium precursor in the interpretation of iodine behavior will be eximined extensively in the present run in an effort to resolve previous discrepancies. Studies of iodine behavior can be continued after shutdown of the hydroclone system if required. An electrolytic process for removal of nickel from fuel solution has been developed through the laboratory and engineering scale except for the design and testing of a cell suitable for radioactive environments. (auth)
Date: June 17, 1959
Creator: Burch, W. D.; Haas, P. A. & McNees, R. A.
Object Type: Report
System: The UNT Digital Library
Removal of cesium from uranium recovery process wastes (open access)

Removal of cesium from uranium recovery process wastes

The Uranium Recovery Process (TBP Process) at Hanford extracts and decontaminates uranium from the Metal Waste produced in the Bismuth Phosphate Process. Aqueous waste, approximately equal in volume to that of the Metal Waste itself, results from the process. Although of several years' age, these wastes are still sufficiently radioactive that they must be returned to underground tanks for storage. For several years aqueous wastes of low radioactive content have been discharged to ground at Hanford. Polyvalent cations are strongly absorbed by the soil. Monovalent cations are poorly absorbed if present in solutions of high salt content. Ground waters migrate toward the Columbia River very slowly. These observations point out the desirability of removing, from wastes to be cribbed, those long-lived radioactive constituents which are poorly absorbed by soil. Cesium (Cs-137) and strontium (Sr-90) are the principal constituents of Hanford wastes which possess these characteristics. Strontium, while more hazardous biologically, is of somewhat less concern than cesium because it is better absorbed from high-salt solutions by soils. This report describes research done to develop on inexpensive process for the removal of fission products, especially cesium, from Uranium Recovery Process Wastes. 4 refs., 13 tabs.
Date: May 17, 1954
Creator: Burns, R. E.; Brandt, R. L. & Clifford, W. E.
Object Type: Report
System: The UNT Digital Library
THE ISOLATION AND PURIFICATION OF AMERICIUM (open access)

THE ISOLATION AND PURIFICATION OF AMERICIUM

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Date: April 17, 1956
Creator: Campbell, D.O.
Object Type: Report
System: The UNT Digital Library
Recent Advances in Millimicrosecond Counting Techniques (open access)

Recent Advances in Millimicrosecond Counting Techniques

The author describes some of the changes that are now occurring or are likely to occur quite soon in the fast counting techniques. The author draws heavily on the information and advice of Dr. Clyde Wiegand and Mr. Quentin Kerns of the University of California Radiation Laboratory. The techniques the author mentions should be quite useful in several different types of experiments. The fast conicidence techniques are principally used for reducing background from accidental coincidences, for measuring times of flight of particles from one counter to another, and for measuring the life times of unstable particles.
Date: April 17, 1956
Creator: Chamberlain, Owen
Object Type: Report
System: The UNT Digital Library
The Velocity-Selecting Cerenkov Counter (open access)

The Velocity-Selecting Cerenkov Counter

None
Date: April 17, 1956
Creator: Chamberlain, Owen & Weigand, Clyde
Object Type: Report
System: The UNT Digital Library