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Economic Evaluation of a 300 Mwe Fast Supercritical Pressure Power Reactor
Report regarding Hanford Laboratories' 300 Mwe fast supercritical pressure power reactor. This includes descriptions of the plant and reactor, their operations, safety systems, and plant economics. Appendices begin on page 107.
Date:
December 9, 1963
Creator:
Aase, D. T.; Fox, J. C.; Hennig, R. J.; Peterson, R. E.; Stewart, S. L. & Toyoda, K. G.
System:
The UNT Digital Library
MERCURY PUMP DEGRADATION.
None
Date:
January 1, 1963
Creator:
Abramson, P.B.
System:
The UNT Digital Library
NEUTRON TISSUE DOSE AT LARGE DISTANCES FROM AN ELEVATED UNSHIELDED REACTOR
The neutron tissue dose at large distances from a fission source was studied by using a water-filled phantom and four different detectors: a BF/sub 3/ counter, a polyethylenelined ethylene-filled proportional counter, indium foils, and nuclear emulsions. The source of fission neutrons was the ORNL Health Physics Research Reactor which was attached to a hoist which was in turn installed on a 1530-foot tower. The reactor could be operated at any elevation from 27 to 1500 ft. The phantom studies were made at horizontal distances from 250 to 1500 yards from the tower. Dose contributions from recoil protons H/sup 1/ (n, gamma )D/sup 2/ and N/sup 14/(n,p)C/sup 1 reactions are considered. (auth)
Date:
March 11, 1963
Creator:
Aceto, H. Jr.; Pick, M.A. & Stephens, L.D.
System:
The UNT Digital Library
Reactor Development Program Progress Report: April 1963
Report issued by the Argonne National Laboratory discussing progress made by the Reactor Development Program during April 1963. Reactor physics, experiments, and safety studies are presented. This report includes tables, and illustrations.
Date:
May 15, 1963
Creator:
Adams, R. M. & Glassner, A.
System:
The UNT Digital Library
Reactor Development Program Progress Report: March 1963
Report issued by the Argonne National Laboratory discussing progress made by the Reactor Development Program during March 1963. Reactor physics, experiments, and safety studies are presented. This report includes tables, and illustrations.
Date:
April 15, 1963
Creator:
Adams, R. M. & Glassner, A.
System:
The UNT Digital Library
Geology and Coal Resources of the Salyersville North Quadrangle, Magoffin, Morgan, and Johnson Counties, Kentucky
From introduction: The U.S. Geological Survey has conducted investigations of the geology and coal resources of the area in and adjacent to the Salyers-ville North quadrangle in the Eastern Kentucky coal field (fig. 7). The Salyersville North quadrangle lies between lat. 3745' and 37052'30'' N., and long. 8300' and 83 07'30'' E.; it is a 71/2-minute quadrangle in the southeast quarter of the Dingus 15-minute area which also includes the Dingus, Lenox, and White Oak 7 -minute quadrangles (fig. 8). The present report is the second for the 15-minute Dingus area; a report by Adkison (1957) has been published for the White Oak quadrangle and a third report is in preparation for the Lenox quadrangle. Other published reports for quadrangles in the vicinity are those by Englund (1955) for Cannel City to the west; Bergin (1962) for Seitz to the southwest; and Hauser (1953) for Paintsville to the east.
Date:
1963
Creator:
Adkison, W. L. & Johnston, J. E.
System:
The UNT Digital Library
Polymerization in Solid Solutions of Acrylamide in Propionamide
It has previously been shown that the polymer formed in solid state polymerization of acrylamide is amorphous in spite of the fact that the reaction takes place within a crystalline solid. The stage at which it becomes amorphous is not known at present. Work with dilute solid solutions of acrylamide in propionamide suggests that this occurs after the addition of, at most, a very few monomer units.
Date:
March 26, 1963
Creator:
Adler, G. & Reams, W.
System:
The UNT Digital Library
High Dilution On-Stream Isotopic Tracers Annual Report: 1962
Introduction: The general aims of this work were to further the practical applications of radioisotope technology.
Date:
1963?
Creator:
Aebersold, Paul C. & Bizzell, Oscar M.
System:
The UNT Digital Library
Army Gas-Cooled Reactor Systems Program Quarterly Progress Report: July 1 - September 30, 1963
Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.
Date:
November 15, 1963
Creator:
Aerojet-General Corporation
System:
The UNT Digital Library
Army Gas-Cooled Reactor Systems Program Quarterly Progress Report: July 1 - September 30, 1963
Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.
Date:
November 15, 1963
Creator:
Aerojet-General Corporation
System:
The UNT Digital Library
Army Gas-Cooled Reactor Systems Program Quarterly Progress Report: October 1 - December 31, 1963
Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.
Date:
February 15, 1963
Creator:
Aerojet-General Corporation
System:
The UNT Digital Library
The Mechanism of Desalination by Reverse Osmosis
Report describing the various parameters operative in fabricating desalination membranes for the Reverse Osmosis Process and the mechanism of separation. The bulk of the membrane contains huge quantities of capillary water which permits the movement of water through the body of the membranes at extremely rapid rates, there being essentially no pressure drop in this portion of the membrane.
Date:
1963
Creator:
Aerojet-General Corporation
System:
The UNT Digital Library
Old pile HCR operating temperatures
A study was made to determine operating temperatures of old pile HCR sheaths. The calculations were performed with the aid of a FORTRAN coded program for the IBM 7090. The difficulty of determining the correct value for the contact coefficient between the HCR and the graphite channel at any point in the channel length resulted in performing the calculations in a parametric style. The independent system parameters were varied during the calculations. These parameters are diametral spacing between the poison rings and the outer aluminum sheath, heat generation rate or reactor power level, the heat transfer contact coefficient between the rod and the graphite channel, and the cooling water temperature or cooling flow rate. For contact coefficients between 200 and 700 Btu/hr -- ft{sup 2} -- {degree}F and for diametral clearances around the poison of 5 mils to 20 mils, the maximum sheath temperature was calculated to vary between 350{degree}F and 650{degree}F. The dependence of sheath temperature upon the rod coolant temperature or coolant flow rate was found to be small enough to be neglected in the normal flow range of 12 gpm to 15 gpm. For a given increase of the average coolant temperature, the maximum sheath temperature increased …
Date:
October 10, 1963
Creator:
Agar, J. D.
System:
The UNT Digital Library
Proposed graphite coring patterns for B, D, F, DR, and H Reactors
Heat transfer calculations were performed with the aid of the IBM 7090 to determine whether or not feasible graphite channel coring patterns could be adopted at the five older Hanford Reactors. The purpose of front and rear process channel coring is to significantly reduce or eliminate net expansion of the fringe graphite by raising the operating temperature above the annealing temperature of 300{degree}C. The results of the study show that such coring patterns are possible. Also, it was found to be possible, and indeed desirable, to standardize the patterns into one front face coring pattern and one rear face coring pattern for all five of the reactors: B, D, F, DR, and H. The resulting coring patterns are presented. These coring patterns will significantly reduce the net rate of expansion in the filler blocks and consequently reduce the inlet and outlet humps in the process channels. This will allow standard 8-inch fuel elements to be charged in all tubes. The afore-mentioned coring patterns will limit the pile gas atmosphere to a range of between 90% He - 10% CO{sub 2} and 100% He. If a greater percentage of CO{sub 2} were used following the adoption of the coring patterns, the …
Date:
June 20, 1963
Creator:
Agar, J. D.
System:
The UNT Digital Library
Separation of Beryllium from Fission Products in a Nitrate Medium - Preliminary Experiments Using Solvent Extraction
Preliminary experiments using acetylacetone in the presence of ethylenediaminetetraacetic acid to separate major quantities of beryllium from fission products are reported. Using 2M beryllium solutions, decontamination factors of the order of 10/sup 3/ were obtained with trace quantities of the more important fission products. This is sufficiently encouraging for the work to be repeated at higher activity levels.
Date:
March 1963
Creator:
Aggett, J
System:
The UNT Digital Library
Final report: PITA-18 use of nonpoisonous splines for longitudinal flux traversing
Optimization of the reactor process involves the knowledge of the longitudinal flux distribution on a semicontinuous, routine basis. The nonpoisonous spline was proposed as a way for obtaining flux traverses at any time during reactor operation, in virtually any location in the core. This report summarizes the findings of a feasibility study conducted in conjunction with PITA-18 and thus serves as a termination of the test phase of spline traversing.
Date:
May 1, 1963
Creator:
Albertson, D. G. & Bowers, C. E.
System:
The UNT Digital Library
Tube-To-Tubesheet Welding Development Programs to 30 Megawatt Prototype Sodium Intermediate heat Exchanger and Steam Generator
Special welding techniques for joining Inconel weld overlays on type 316 stainless steel tubesheets and channels are described. The program for the development of the required welding procedures are divided into three specific programs: overlaying Inconel filler Metal 82 on type 316 stainless steel, welding type 316 stainless steel tubes to a type 316 stainless steel tubesheet, and welding Inconel-type 316 stainless steel composite tubes to Inconel weld overlaid type 316 tubesheets. Shock tests are described which attempt to assimilate the most drastic thermal transient that could occur in both units and to evaluate the effect of the resulting stresses on the Inconel overlay and the tube-to-tubesheet welds. (N.W.R.)
Date:
1963
Creator:
Alco Products (Firm).
System:
The UNT Digital Library
THE AVERAGE ENERGY AND ANGULAR MOMENTUM REMOVED FROM Dy COMPOUND NUCLEI BY NEUTRONS AND PHOTONS
Excitation functions are presented for many heavy-ioninduced (HI) reactions that produce Dy/sup 149/, Dy/sup 150/, and Dy/sup 151/. Projectiles were C/sup 12/, N/sup 14/, N/sup 16/, O/sup 16, O/sup 18/, F/sup 1 9/, and Ne/sup 20/ of 4 to 10.4 Mev per amu. The reactions studied are all of the type (HI,xn), where x ranges from 3 to 9. A large fraction of the total reaction cross section is accounted for by these (HI,xn) reactions --9/10 at approximately 45 Mev to 1/2 at approximately 105 Mev. An analysis to obtain the energy of the first neutron is presented. Comparison of the results of this analysis to angular-distribution studies suggests that each neutron removes 2 to 4 h units of angular momentum. The relation between the average total photon energy and the average angular momentum removed by photons is obtained. Comparison with the average photon energy from other work leads to an average of 1.8 plus or minus 0.6 h for the angular momentum removed by each photon. The excitation energy E/sub j/ of the lowest-lying state of spin J was estimated. (auth)
Date:
January 1, 1963
Creator:
Alexander, John M. & Simonoff, Gabriel N.
System:
The UNT Digital Library
Solvent Extraction Processes for the Recovery and Separation of Uranium and Thorium - a Literature Survey
A summary of the available literature on the development of the various processes for the separation of uranium and thorium from aqueous nitrate solutions is presented. Flowsheets are given corresponding to the various stages in the development of the Thorex processes.
Date:
August 1963
Creator:
Alfredson, Peter George & Farrell, M. S.
System:
The UNT Digital Library
Tension properties of tie rods. Part No. 944C732 spec. grade. Quality control request No. 274
None
Date:
December 16, 1963
Creator:
Allison, H. & Zibritosky, G.
System:
The UNT Digital Library
Neutron Diffraction Studies at the Puerto Rico Nuclear Center
A neutron diffraction program was initiated recently at the Puerto Rico Nuclear Center. The two double crystal spectrometers in use were assembled with the aid of staff members of the Brookhaven National Laboratory. The first research problem to be completed was a single crystal structure analysis of CaWO4. Choosing the origin at the 4(a) tungsten site in the tetragonal I41/a cell. the 16(f) oxygen parameters were found to be as follows: x=0.2413 ± 0.0005, y=0.1511 ± 0.0006, z=0.0861 ± 0.0001. Anisotropic temperature parameters were also determined for all atoms in the least squares analysis of the structure. The magnetic structure of CuSO4 has been determined in a continuation of a study started at Brookhaven in collaboration with Dr. P.J. Brown. Using the Wollan-Koehler-Bertaut notation, the antiferromagnetic spin ordering mode in the orthorhombic Pbnm cell is Ax, with the spin axis parallel to a. A moment of approximately 1 μB was found for the Cu2_ ion. The crystal structure of BaNiO2 was re-examined in a neutron powder diffraction study, and it was found that the earlier x-ray study of Lander is essentially correct. An alternative oxygen arrangement, for which x-rays would not have been very sensitive, had been suspected. BaNiO2 was …
Date:
October 15, 1963
Creator:
Almodovar, I; Bielen, H. J. & Frazer, B. C.
System:
The UNT Digital Library
A Perturbation Method for Solving the Angle Dependent Nucleon-Meson Cascade Equations
A method is described for obtaining an approximate solution to the equations describing a nucleon-meson cascade by using the angular dependence of the secondary particle production kernels as a perturbation. The usefulness of the method lies in the fact that in a slab geometry the equations that must be solved numerically are essentially the same as those that are used in the straight-ahead approximation and have been solved previously. (auth)
Date:
July 30, 1963
Creator:
Alsmiller, R. G., Jr. & Alsmiller, F. S.
System:
The UNT Digital Library
Nucleon-Meson Cascade Calculations: Shielding Against an 800-Mev Proton Beam
Nucleon-meson cascade calculations were carried out and the dose as a function of depth was obtained for an 800-Mev proton beam incident on a shield. The physical properties used for the shielding medium are only a rough approximation to the properties of any particular medium. Muon, neutron, pion, and proton dose rates and fluxes are listed. (auth)
Date:
February 21, 1963
Creator:
Alsmiller, R. G., Jr. & Murphy, J. E.
System:
The UNT Digital Library
Nucleon-Meson Cascade Calculations: The Star Density Produced by a 24-Gev Proton Beam in Heavy Concrete
The nuclear star density produced by a 24-Bev proton beam in a material having approximately the properties of heavy concrete is calculated. A comparison is made with experimental measurements made at CERN; but, since the quantity that can be calculated is not the same as that measured, no firm conclusions can be drawn. Proton, neutron, pion, and muon intensities are plotted vs. distance as are star densities. (auth)
Date:
January 21, 1963
Creator:
Alsmiller, R. G., Jr. & Murphy, J. E.
System:
The UNT Digital Library