Hedstrom Plot for the Calculation of Laminar Flow Pressure Drop for Bingham Plastic Materials with Hedstrom Numbers From 0 TO 10$sup 1$$sup 5$ (open access)

Hedstrom Plot for the Calculation of Laminar Flow Pressure Drop for Bingham Plastic Materials with Hedstrom Numbers From 0 TO 10$sup 1$$sup 5$

None
Date: June 20, 1957
Creator: Thomas, D. G.
Object Type: Report
System: The UNT Digital Library
PROGRESS REPORT FOR THE PERIOD JANUARY 1, 1953 THROUGH MARCH 31, 1953 (open access)

PROGRESS REPORT FOR THE PERIOD JANUARY 1, 1953 THROUGH MARCH 31, 1953

None
Date: April 20, 1953
Creator: Smothers, W.J.
Object Type: Report
System: The UNT Digital Library
BEVATRON RESEARCH MEETING III - BEVATRON THEORY (open access)

BEVATRON RESEARCH MEETING III - BEVATRON THEORY

Despite the essentially independent development of the Cosmotron and Bevatron, these two accelerators have general specifications which are the same within a factor of 2-3 in their pertinent characteristics. An electron analogue of the Bevatron would be an electron synchrotron operating in the 5 kev to 3 Mev range.
Date: October 20, 1953
Creator: Smith, Lloyd
Object Type: Report
System: The UNT Digital Library
REQUIREMENTS FOR RAW MATERIALS IN AN EXPANDING NUCLEAR POWER ECONOMY (open access)

REQUIREMENTS FOR RAW MATERIALS IN AN EXPANDING NUCLEAR POWER ECONOMY

The need for breeding does not appear to be highly cost for a moderately optimistic expanding nuclear power economy between 1960 and 2000. Since the expansion rate of the US nuclear economy is assumed to be high at least 2/3 of the U-235 recovered from natural uranium is used to supply reactor inventory. It is the remaining 1/3 of the available U-235 that can be saved by breeder breeders or a breeder and converter are the doubling time and a parameter expressing the total fissile inventory per magawatt of electricity. In fact, the need for new raw material in any given year is reduced more by specific power than by changing from a converter to a value of total inventory per magawatt of electricity and the content and value of plutonium or U-233 than on raw material cost. The use of 12% vs. 4% annual lease charge can change the inventory costs more significantly than either the Pu (or U-233)/U-235 value ratio or raw material cost. Net fuel burn costs vary more with the product of net conversion ratio and Pu (or U-233)/U-235 value ratio than with the cost of raw material. (auth)
Date: January 20, 1959
Creator: Arnold, E.D. & Ullmann, J.W.
Object Type: Report
System: The UNT Digital Library
Monthly Progress Report for the Period June 1 to 30, 1958 (open access)

Monthly Progress Report for the Period June 1 to 30, 1958

Progress in the design and development of the Yankee Power Reactor is briefly reviewed. (For preceding period see YAEC-79.) (T.R.H.)
Date: July 20, 1958
Creator: Coen, I. H. & Barbe, R. W.
Object Type: Report
System: The UNT Digital Library
PROBLEMS OF LEACHING AND DIGESTION OF URANIFEROUS SLAGS AND ALLOYS. Progress Report No. 12 for April 1952 (open access)

PROBLEMS OF LEACHING AND DIGESTION OF URANIFEROUS SLAGS AND ALLOYS. Progress Report No. 12 for April 1952

None
Date: May 20, 1952
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Zirconium Pilot Plant Research and Development. Progress Report (open access)

Zirconium Pilot Plant Research and Development. Progress Report

A summary of the work which was done on the small pilot plant during the week's operation shows the following: (1) High vaporization rates can be obtained from a vibrating flash plate. (2) Feeding powder to the plate at a constant and controllable rate presented some difficulty. This may be overcome by pumping between Victoprene seals, proper outgassing of the powder, using a smaller diameter screw, and sloping the feed screw upward to avoid translation of the powder by vibration. (3) Deposition rates could not be properly studied because of high noncondensable pressures. There is an indication that too high a flow rate favors the deposition of ZrI/sub 2/ if the filiment temperature is too low. (4) No corrosion of the flash plate was evidenced during the short period the plant was in operation. A thorough study of corrosion must be made, however, since the entire process may depend on the durability of the flash plate. (5) This type of equipment offers a means of rapidly obtaining good data at a low cost on the fundamentals of an iodide-flow process for the production of zirconium metal. (auth)
Date: November 20, 1951
Creator: Dryden, C. E.; Accountius, O. E.; Black, D. G.; Finney, B. C.; Gruber, B. A.; Jurevic, W. G. et al.
Object Type: Report
System: The UNT Digital Library
Use of Nitrogen as Inert Gas Backing in Welding Austenitic Stainless Steels (open access)

Use of Nitrogen as Inert Gas Backing in Welding Austenitic Stainless Steels

None
Date: August 20, 1956
Creator: Leonard, W. J.
Object Type: Report
System: The UNT Digital Library
Test of HRT Recombiners (open access)

Test of HRT Recombiners

Tests of the HRT fuel and blanket recombiners at several gas concentrations and steam rates disclosed satisfactory efficiency at approximately design conditions. At lower gas concentrations and steam fiow rates a small recombiner downstream from the condenser is necessary to maintain 100% recombination. It is recommended that the platinized catalyst in the fuel and blanket HRT recombiners not be replaced, and that a small recombiner be installed in the 1-in. off-gas line from each recombiner condenser. (auth)
Date: September 20, 1957
Creator: Hannaford, B. A.
Object Type: Report
System: The UNT Digital Library
Progress Report on Zirconium Pilot Plant Research and Development (open access)

Progress Report on Zirconium Pilot Plant Research and Development

None
Date: September 20, 1951
Creator: Accountius, O. E.; Black, D. G.; Dryden, C. E.; Finney, B. C.; Gruber, B. A.; Jurevic, W. G. et al.
Object Type: Report
System: The UNT Digital Library
FUEL MELTING EXPERIMENT-IRRADIATION REQUEST ORNL-MTR-28, PHASE A (open access)

FUEL MELTING EXPERIMENT-IRRADIATION REQUEST ORNL-MTR-28, PHASE A

None
Date: June 20, 1956
Creator: Neill, F H
Object Type: Report
System: The UNT Digital Library
THE USE OF TRI-n-OCTYLPHOSPHINE OXIDE IN THE SOLVENT EXTRACTION OF THORIUM FROM ACIDIC SOLUTIONS (open access)

THE USE OF TRI-n-OCTYLPHOSPHINE OXIDE IN THE SOLVENT EXTRACTION OF THORIUM FROM ACIDIC SOLUTIONS

Thorium is readily extracted by a solution of tri-noctylphosphine oxide in cyclohexane from either acidic nitrate or chloride solutions. The maximum extraction coefficient in a nitrate medium is 380 as compared to 1300 for a chloride solution. In nitrate media the extraction coefficient is relativelv unaffected by changes in the anion concentration. In chloride media the coefficient varies directly with increasing chloride concentration, i.e., from about 0.4 in one molar chloride to the maximum in 7 to 10 molar. The acid concentration should be at least one molar. Thorium is not appreciably extracted from sulfate solutions. The extraction coefficient is of the order of 0.3. The addition of nitrate or chloride increases the coefficient sufficiently so that essentially 99% of the thorium can be extracted in a single equilibration. In perchlolate systems the extractlon is most efficient in one molar acid. The maximum (The above was unscabble material)
Date: November 20, 1958
Creator: Ross, W.J. & White, J.C.
Object Type: Report
System: The UNT Digital Library
MANUAL FOR THE PREPARATION OF SIMULATED FUEL REPROCESSING WASTE SOLUTION (open access)

MANUAL FOR THE PREPARATION OF SIMULATED FUEL REPROCESSING WASTE SOLUTION

Preparation of synthetic wastes from the processing of aluminum-clad natural uranium, aluminum-enriched uranium alloy, zirconium-uranium, stainless steel-UO/sub 2/, and stainless steel-UO/sub 2/-MgO fuel elements is described. These preparations will be used in waste disposal studies. (auth)
Date: June 20, 1958
Creator: Lacy, W.J.
Object Type: Report
System: The UNT Digital Library
MSPR IN-PILE LOOP ORNL-MTR-44 DESIGN AND OPERATING CONDITIONS (open access)

MSPR IN-PILE LOOP ORNL-MTR-44 DESIGN AND OPERATING CONDITIONS

A brief description and the planned operating parameters of the ORNL-MTR- 44 MSPR in-pile loop are given tegether with the operating characteristics of the major components of the loop. (auth)
Date: October 20, 1958
Creator: Conlin, J.A.
Object Type: Report
System: The UNT Digital Library
PREDICTED VAPOR PRESSURES IN THE HRT (open access)

PREDICTED VAPOR PRESSURES IN THE HRT

Radiolytic gas concentration in the HRT as a function of operating power and temperature have been calculated for the conditions of Run 18. The partial pressure of the radiolytic gas was estimated for the various conditions. The maximum total vapor pressure (the maximum summation of the radiolytic gas partial pressures excess oxygen partial pressures and D2O vapor pressure) was found to exist at the core and blanket outlets for all avcrage temperatures greater than 250 C. Below 240 C at some recombination rate constants and power levels, the maximum pressure will be highest at the heat exchanger exit. In the calculations the transfer of radiolytic gas between the core and blanket systems was neglected. The simplification is equivalent to saying that the radiolytic gas transfer between the systems is equal. The results of the calculations show that this is nearly true when 60% of the total power is generated in the core. The effect of pump-up in each system was included. (auth)
Date: April 20, 1959
Creator: Gift, E.H.
Object Type: Report
System: The UNT Digital Library
SOME INVERSE CHARACTERISTIC VALUE PROBLEMS WHICH ARISE IN THE STUDY OF SIMPLE MOLECULES (open access)

SOME INVERSE CHARACTERISTIC VALUE PROBLEMS WHICH ARISE IN THE STUDY OF SIMPLE MOLECULES

None
Date: October 20, 1955
Creator: Downing, A.C. & Householder, A.S.
Object Type: Report
System: The UNT Digital Library
Studies in the Carbonate-Uranium System. Part 3. Spectrophotometric Investigation of the Carbonate-Uranyl Complexes (open access)

Studies in the Carbonate-Uranium System. Part 3. Spectrophotometric Investigation of the Carbonate-Uranyl Complexes

None
Date: August 20, 1951
Creator: Blake, C. A.; Lowrie, R .S.; Brown, K. B. & Hill, D. G.
Object Type: Report
System: The UNT Digital Library
TRANSMISSION-LINE MISSILE ANTENNAS (open access)

TRANSMISSION-LINE MISSILE ANTENNAS

Protruding rocket antennas of low silhouette are examined using transmission-line concepts. The theory was developed specifically for nondissipative terminations and line sections; however, the formulas are readily generalized to include ohmic losses in the lines and terminations. Adaptive computations may be made for conductors other than circular and the theory may be used to analyze antennas of other missiles. (J.R.D.)
Date: November 20, 1958
Creator: King, R.W.P.; Harrison, C.W. Jr. & Denton, D.H. Jr.
Object Type: Report
System: The UNT Digital Library
The Possibility Of "Freezing-in" Radiation Damage Effects in Simple Metals (open access)

The Possibility Of "Freezing-in" Radiation Damage Effects in Simple Metals

None
Date: June 20, 1950
Creator: Cooper, E. P. & Mills, M. M.
Object Type: Report
System: The UNT Digital Library
Energy Transfer Between Modified Maxwell Distributions (open access)

Energy Transfer Between Modified Maxwell Distributions

S>A convenient modified form of Maxwell distribution is chosen. The modified expressions for the energy transfer from the ions to the electrons in a plasma and the bremsstrahlung from the electrons are calculated. Using the expressions some possible steady-state conditions for the ion and electron gases are derived and compared with those for the usual Maxwell distributions. (anth)
Date: September 20, 1956
Creator: Greyber, H. D.
Object Type: Report
System: The UNT Digital Library
Monthly Progress Report for the Period November 1 to 30, 1958 (open access)

Monthly Progress Report for the Period November 1 to 30, 1958

Work directed toward developing a stainless steel clad UO/sub 2/ fuel element is reported. Methods are being developed for utilizing chemical poisoning for reactor in the reference environment. The design and development of mechanical features of fuel assemblies, control rods, baffles, the support structure, the reactor vessel closure, and fuel handling tools are presented. (For preceding period see YAEC-101.) (W.L.H.)
Date: December 20, 1958
Creator: Garbe, R. W. & Walchli, H. E.
Object Type: Report
System: The UNT Digital Library
Shielding for the Low Power Research Reactor (open access)

Shielding for the Low Power Research Reactor

None
Date: February 20, 1951
Creator: Neustadt, M.
Object Type: Report
System: The UNT Digital Library
The Relationship Between the Surface Appearance and Depth of Damage of Subfabric and Bare Skin Burns Produced by Radiant Thermal Energy (open access)

The Relationship Between the Surface Appearance and Depth of Damage of Subfabric and Bare Skin Burns Produced by Radiant Thermal Energy

In a series of 600 cutaneous burns in swine produced by radiant thermal energy at 0.5 and 5.0 sec exposure time, the relationship of thc surface appearance and the depth of damage of bare skin and subfabric burns was investigated. The fabrics used were a black and a gray sateen weighing 8 to 9 oz/ yd/sup 2/. It was found that there is no significant difference in the 1+ burns whether produced on bare skin or beneath fabric, either at 0.5 or 5.0 sec exposure. However, the 2+ subfabric burns average about 0.1 mm deeper in dermal damage than thc same grade barn of bare skin. Nevertheless, the protection afforded by fabric is found to be nearly the same whether the burns were judged by surface appearance or microscopically by depth of damage. (auth)
Date: February 20, 1958
Creator: Berkley, K. M.
Object Type: Report
System: The UNT Digital Library
SODIUM FLUORIDE AS A SPECTROSCOPIC CARRIER FOR PLUTONIUM METAL ANALYSIS (open access)

SODIUM FLUORIDE AS A SPECTROSCOPIC CARRIER FOR PLUTONIUM METAL ANALYSIS

A pyroelectric carrier distillation method, using sodium fluoride as a spectroscopic carrier, was developed for the impurity analysis of plutonium metal. (auth)
Date: April 20, 1959
Creator: Johnson, A.J. & Vejvoda, E.
Object Type: Report
System: The UNT Digital Library