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MUSC Environmental Biosciences Progress Report
3
ORNL Radioisotope Distirbution Program Progress Report
2
Advanced Cuttings Transport Study Quarterly Report
1
Army Gas-Cooled Reactor Systems Program Progress Report
1
CO2 Capture by Absorption With Potassium Carbonate Quarterly Report
1
Cross-Roll Flow Forming of ODS Alloy Heat Exchanger Tubes For Hoop Creep Enhancement Quarterly Report
1
Development of On-line Instrumentation and Techniques to Detect and Measure Particulates Quarterly Report
1
Fiscal Year 2000
1
Fundamentals of Energy Transport in Nanofluids Annual Report
1
LLW Notes
1
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H.E.W. - 300 Area - Metal turnings - Fire hazard
This memorandum discusses means to extinguish magnesium fires in metal turnings at the Hanford Engineer Works 300 Area. The storage of metal turnings in 55 gallon drums presented a fire hazard, for which an effective means for extinguishing the fire had not been presented. This memorandum is dated July 1943. (JL)
Date:
July 31, 1943
Creator:
Huey, W. R.
Object Type:
Report
System:
The UNT Digital Library
Production Test No. 105-1-P: Effect of pile operation on the characteristics of the graphite filler (Wigner disease)
None
Date:
July 31, 1944
Creator:
Crane, P.W.
Object Type:
Report
System:
The UNT Digital Library
GENERAL RESEARCH REPORT FOR APRIL 1-JUNE 26, 1950. (Radium Volume)
None
Date:
July 31, 1950
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
RECOVERY OF URANIUM FROM NORTH DAKOTA LIGNITES. Final Report
None
Date:
July 31, 1950
Creator:
Ewing, R. A.; Adam, H. W.; Miles, F. W.; Bearse, A. E. & Richardson, A. C.
Object Type:
Report
System:
The UNT Digital Library
Chemical development Separations Technology Unit. Progress report
The Redox Plant operated at a 76.7% time efficiency (IAF basis) and averaged 3.16 tons of uranium per operating day during the month. During the period from July 4 through July 13, 38,000 gallons of 72% ANN from Tygon-lined storage tank SS-112 were used in aqueous salt solution make-ups with some emulsion difficulty and fission-product carry-over resulting. New ANN, from stainless-steel tanks, was used for the balance of the month. An extensive (thermally) hot 60% HNO{sub 3} cleanout was given to the IA, IB, 2D, 3D, 2A, and 3A columns and associated salt solution head tanks to prepare the solvent-extraction battery for operation using 90-day `cooled` uranium. Continuous cross-over oxidation to improve 2A Column waste losses, and employment of KOH (vice NaOH) in 2DS, ICU, and 2EU butt additions to minimize Na in 3EU, were begun concurrently on July 20. Aged (90-day) uranium in head-end treated feed batches, was started to the IA Column on July 21, with early data indicating adequate two-cycle decontamination for both uranium and plutonium.
Date:
July 31, 1952
Creator:
Woodfield, F. W.
Object Type:
Report
System:
The UNT Digital Library
Electromagnetically Enriched Isotopes Inventory, July 31, 1952
None
Date:
July 31, 1952
Creator:
Keim, C. P.; Normand, C. E. & Weaver, B.
Object Type:
Report
System:
The UNT Digital Library
TECHNICAL PROGRESS REPORT FOR FIRST QUARTER, MAY 1 TO JULY 31, 1952 ON INVESTIGATIONS FOR THE PRODUCTION OF THORIUM METAL BY FUSED SALT ELECTROLYSIS
None
Date:
July 31, 1952
Creator:
Sibert, M.E. & Steinberg, M.A.
Object Type:
Report
System:
The UNT Digital Library
The Dependency of Reactivity of Burn-up in Fast Reactors
In fast reactors the poisoning effects of fission products are reduced because of relative low capture cross sections at high energies. In addition, in fluid fuel reactors there is the possibiity of removing them by processing. If plutonium production is of secondary importance to power production, then higher burnup of fuel is possible and dependency of reactivity on burnup becomes a problem of interest. One-group calculations are performed as a first step in understanding the relative effects of the initial breeding ratios, enrichment, and fissin product and heavy isotope concentration.
Date:
July 31, 1953
Creator:
Sehnert, R. H.
Object Type:
Report
System:
The UNT Digital Library
PREPARATION OF CARRIER-FREE LANTHANUM-140
None
Date:
July 31, 1953
Creator:
Salutsky, M.L. & Kirby, H.W.
Object Type:
Report
System:
The UNT Digital Library
Absorption Spectra of Plutonium and Impurity Ions in Nitric Acid Solution
The absorption spectra for Pu(III), (IV), (VI), and the red Pu(IV)- peroxy complex were determined in HNO/sub 3/ solution. Extinction coefficients for the above species of Pu were measured. Temperature has little effect on the spectra, but variation of acidity causes shifting of absorption peaks and some changes in the extinction coefficients. The absorption spectra and extinction coefficients in the region 390 to 1200 m mu were measured for chromic, nickelous, manganous, calcium, lanthanum, aluminum, ferrous. ferric, and permanganate ions in HNO/sub 3/ solutions. In addition, the effects of nitrite, oxalic acid, sulfamic acid, hydrogen peroxide, and various HNO/sub 3/ concentrations on the extinction coefficients of some of these ions were determined. The chromic, nickelous, ferrous, and permanganate ions, and ferric ion with oxalic acid, have sufficiently high extinction coefficients to cause inaccuracies in valence determinations of Pu in solutions containing high concentrations of these ions, unless corrections are made. (auth)
Date:
July 31, 1956
Creator:
Myers, M. N.
Object Type:
Report
System:
The UNT Digital Library
DYNAMIC LOADING OF RUPTURE DISCS
None
Date:
July 31, 1956
Creator:
Leibson, M.J.
Object Type:
Report
System:
The UNT Digital Library
Gas Cooled Nuclear Reactor Study. Final Report
An investigntion was made of the performance of a gas-cooled reactor, designed to provide a source of high temperature heat to a stream of helium. This reactor, in turn, is used as a source of heat for the air stream in a gas- turbine power plant. The reactor design was predicted primarily on the requirement for transferring a large amount of heat to the helium stream with a pressure drop low enough that it will not represent a major loss of power in the power plant. The mass of uranium e uired far criticality under various circumstances was investigated by multigroup calculations, both on desk calculators and on an IBM-704 machine. The gasturbine power plant perfarmance was studied based on a Studebaker-Packard-designed gas-turbine power plant for the propulsion of destroyer-escort vessels. A small experimental program was carried out to study some effects of helium on graphite and on structural steels. (auth)
Date:
July 31, 1956
Creator:
Thompson, A. S.
Object Type:
Report
System:
The UNT Digital Library
HRP Dynamic Slurry Corrosion Studies: Quarter Ending July 31, 1956
None
Date:
July 31, 1956
Creator:
Compere, E. L.; Savage, H. C.; Reed, S. A.; Moore, G. E.; Warner, R. M.; Pierce, R. M. et al.
Object Type:
Report
System:
The UNT Digital Library
HRP Dynamic Solution Corrosion Studies for Quarter Ending July 31, 1956
None
Date:
July 31, 1956
Creator:
Griess, J. C.; Savage, H. C.; English, J. L.; Greeley, R. S.; Buxton, S. R.; Warner, R. M. et al.
Object Type:
Report
System:
The UNT Digital Library
INHALATION TOXICITY OF ZIRCONIUM COMPOUNDS. I. SHORT-TERM STUDIES
A total of 270 animals of 5 species was exposed by inhalation to compounds of zirconium for 6 hours per day, 5 days per week. One group of animals was exposed to ZrO{sub 2} at an atmospheric concentration of 75 mg. Zr/m{sup 3} for 30 days; another, to 11 mg. Zr/m{sup 3} for 60 days. A third group was exposed to a mist of ZrCl{sub 4} at a level of 6 mg. Zr/m{sup 3} for 60 days. Zirconium oxide produced no significant changes in mortality, growth rate, blood nonprotein nitrogen or fibrinogen, urinary protein, hematological values or histological structure. Zirconium tetrachloride at 6 mg. Zr/m{sup 3} gave questionable changes in blood hemoglobin concentration and red cell counts of dogs and a slight increase in mortality of rats and guinea pigs. Inhaled zirconium compounds deposited primarily in the lung and pulmonary lymph node, with a fraction of a per cent in the bone and considerably less in the soft tissues. (auth)
Date:
July 31, 1956
Creator:
Spiegl, C. J.; Calkins, M. C.; DeVoldre, J. J.; Scott, J. K.; Steadman, L. T. & Stokinger, H. E.
Object Type:
Report
System:
The UNT Digital Library
Report of explosion and fire in hydrogen liquefier apparatus
None
Date:
July 31, 1956
Creator:
Hungerford, T. W.; Lain, J. E. & Beeler, B. M.
Object Type:
Report
System:
The UNT Digital Library
Bibliography on Radiochemical Processing of Irradiated Fuel Elements
This report addresses the bibliography on radiochemical processing of irradiated fuel elements.
Date:
July 31, 1957
Creator:
Eister, W. K.
Object Type:
Report
System:
The UNT Digital Library
A CALCULATION OF THE GAMMA-RAY SPECTRUM OF THE BULK SHIELDING REACTOR
A calculation was performed to determine the highenergy portion of the gamma-ray flux at the surfacc of the uranium-aluminum BSF reactor. The flux was considered to consist entirely of the uncollided flux plus the Comptonscattered flux. The four sources of primary gamma rays included in the calculation were prompt fission gamma rays, capture gamma rays from aluminum, capture gamma rays from uranium, and fission-product decay gamma rays. These sources were divided into four energy groups. Although the assumptions used to calculate the Comptonscattered flux tended to over-estimate the actual spectrum, the calculated results were considerably lower than a previously measured spectrum. (auth)
Date:
July 31, 1957
Creator:
deSaussure, G.
Object Type:
Report
System:
The UNT Digital Library
NEUTRON AND PHOTON TRANSPORT: PLANE, CYLINDER, SPHERE (DIGITAL COMPUTER PROGRAMS)
Digital comnputer Program S constructs neutron and proton transport theory solutions having plane, cylindrical, or spherical symmetry. Lattice detail in geometry, energy, and momentum-angles is flexibleAnisotropic scattering- transfer is neglected. For aircraft nuclear propulsion applications, the initial version of the program developed as the Los Alamos SNG Neutron Code has been generalized to include the effects of time-delayed neutron or photon production and to provide the flux adjoint. The input consists of geometry, material concentrations, collision cross sections, scattering-transfer cross sections, fission multiplication cross sections, inverse period Laplace-timetransform of fission production spectra, and Laplacetime-transform of fixed source distribution. The output includes resctivity, critical size, flux distribution, adjoint distribution, and power distribution. (auth)
Date:
July 31, 1957
Creator:
Duane, B.H.
Object Type:
Report
System:
The UNT Digital Library
Shield Weights
Shield weights were calculated for a number of fast reactors having desirable engineering characteristics using the Shield Optimization code. On the basis of these calculations, a Design Fast Reactor was chosen. This reactor, henceforth known as the PWAR-9, has a 12.75 inch core O.R. with a 2 inch Ni reflector. The reactor-shield weight and weight components for a supersonic mission, 2 man crew compartment, are given in table 1. The rpesent shield design uses U and LiR as shielding materials on the reactor and U and plastic on the crew compartment. No intermediate heat exchanger is used since hot Na is pumped directly to the engines. The dose from the activated Na is taken into account by putting more shielding on the crew compartment. No patch weights on the reactor have been added since it is estimated that little will be needed.
Date:
July 31, 1957
Creator:
Woodsum, H.C. & Rost, E.S.
Object Type:
Report
System:
The UNT Digital Library
Solution Corrosion Group Quarterly Report for the Period Ending July 31, 1957
The second All-Ti loop, 1OOA loop H, was placed in operation for more than 400 hr with UO/sub 2/SO/sub 4/ solution at 250 deg C and -- 1000 psi. A fourth test of the mockup of the Zircaloy-2--stainless steel transition joint used in the HRT reactor vessel was completed. The joint and bellows functioned properly and were leaktight. The series of long-term runs at 200, 250, and 300 deg C with solution proposed for use in the HRT was concluded. Stainless steel and Ti stress specimens exposed during the latter 13,000 hr of these tests gave no evidence of stress-corrosion cracking. Results of a study of the effect of heat treatment on corrosion of type 347 stainless steel are presented. Pretreatment of stainless steel for 100 hr at 250 deg C with oxygenated H/sub 2/O containing 100 or 200 ppm Cr/sup 6+/ as CrO/sub 3/ decreased initial weight losses on subsequent exposures to UO/sub 2/SO/sub 4/ solutions. Stress-corrosion cracking of stainless steel in UO/sub 2/SO/sub 4/ solutions is described. A number of alloys of Zr were corrosion tested in simulated HRT core solutions at 300 deg C. Type 347 stainless steel, surface hardened either by malcomizing or Thermospray 16-C, corroded …
Date:
July 31, 1957
Creator:
Griess, J. C.; Savage, H. C.; English, J. L.; Ulrich, W. C.; Buxton, S. R.; Neumann, P. D. et al.
Object Type:
Report
System:
The UNT Digital Library
Buildup and Decay Factors for Members of the U-232 Decay Chain
Activity ratios for the important members of the U/sup 232/ chain are presented in tabular form. These ratios are presented for initially pure U/sup 232/, initially pure Th/sup 228/ and initially pure Ra/sup 224/.- (auth)
Date:
July 31, 1958
Creator:
Arnold, E.D.
Object Type:
Report
System:
The UNT Digital Library
Quarterly Report of the Solution Corrosion Group for the Period Ending July 31, 1958
6 6 5 4 ; 6 6 5 6 4 8 4 : the chemica: stability of possible fuel solutions, and the results obtained from these runs have been compared with data obtained by others. A solution containing 0.04 m UO/sub 2/SO/ sub 4/, 0.03 m CuSO/sub 4/, 0.03 m NiSO/sub 4/, and 0.023 m D/sub 2/SO/sub 4/ in heavy water was not completely stable at 175 deg C or at other higher temperatures. About 7% of the copper was lost at 175 to 275 deg C, and an additional 9% was lost when the temperature was increased to 300 deg C. In the same solution the nickel solubility decreased by 40% up to 200 deg C and then increased up to 275 deg C and at 300 deg C again decreased. Throughout the run no uranium was lost from solution. A second solution containing 0.01 m UO/sub 2/ SO/sub 4/, 0.02 m D/sub 2/SO/sub 4/, 0.01 m CuSO/sub 4/ and 850 ppm nic kel in heavy water was stable at 300 deg C. However, when an additional 450 ppm of nickel was added to the solution, about 10% of the uranium, 6% of the copper, and 20% more nickel …
Date:
July 31, 1958
Creator:
Griess, J. C.; Savage, H. C.; Greeley, R. S.; English, J. L.; Bolt, S. E.; Buxton, S. R. et al.
Object Type:
Report
System:
The UNT Digital Library
ULTRA HIGH FLUX RESEARCH REACTORS
Verbatim transcriptions of nine seminars on ultra high flux research reactors are revised and collected here. The seminars included: production of transuranic elements, isotope production using high fluxes, high fluxes for neutron diffraction experiments and velocity selector experiments, solid state physics and the materials for high flux reactors, physics of flux-trap and other ultra high flux reactors, and design considerations of aqueous flux-trap reactors. (T.R.H.)
Date:
July 31, 1958
Creator:
Lane, J.A.
Object Type:
Report
System:
The UNT Digital Library