34 Matching Results

Search Results

Results: 1 - 24 next
open access

EGCR EXPERIMENTAL LOOPS, PRELIMINARY DESIGN REPORT

Description: The EGCR was designed to accommodate up to four gascooled experimental loops plus several experimental fuel elements in the open core. Two of the loops will utilize 51/2-in.-O.D. stainless steel tubes passing through the core along an axis which is about 17 in. from the central axis of the core. The other two loops will utilize 91/2-in.-o.d. tubes about 68 in. from the central axis. Inherent safety in the design, facility design, primary loop design, auxiliary systems and equipment design, prim… more
Date: March 27, 1962
Creator: Neill, F.H. & Michelson, C.
Partner: UNT Libraries Government Documents Department
open access

Thermal Stress Testing of Type 1 Fuel Plates

Description: Thermal stress tests on Type 1, SM-1A Core II fuel ele-ment sections were performed to study plate distortion and determine its dependency on temperature distribution, temperature differential, initial flatness, and ripple length. Test results will be correlated with the analytical model and used to predict ripple growth in other plate-type fuel elements. The tests showed that ripple growth is dependent on initial flatness of the plate and that the characteristic shape of ripples is maintained … more
Date: June 27, 1962
Creator: Gebhardt, F. G.
Partner: UNT Libraries Government Documents Department
open access

AN ESTIMATE OF THE EFFECT OF NEUTRON-ENERGY SPECTRUM ON RADIATION DAMAGE OF STEEL

Description: The postulate that the average number of lattice displacements is directly proportional to the available energy is carried one step further; it is assumed that damage to steel (particularly in regard to brittle fracture) is proportional to the number of lattice vacancies that occur. The model, although crude, permits estimation of the relative damage resulting from differences in neutron spectra. The results can be used as a rough method of correcting damage data for the effect of the neutron-e… more
Date: July 27, 1962
Creator: Claiborne, H.C.
Partner: UNT Libraries Government Documents Department
open access

ISOPERIMETRIC AND OTHER INEQUALITIES IN THE THEORY OF NEUTRON TRANSPORT, II

Description: In a prevlous paper, some inequalities occurring in the one-veloclty theory of neutron transport with lsotropic scattering were derived. Some of the previous results are generalized to the case of linearly anisotropic scattering. (auth)
Date: February 27, 1962
Creator: Dresner, L.
Partner: UNT Libraries Government Documents Department
open access

EFFECTIVE CUTOFF ENERGIES FOR B, Cd, Gd, AND Sm FILTERS

Description: Effective energy cutoffs have been calculated on an IBM7090 computer for Cd, Gd, Sm, and B filters as functions of filter geometry, the ratio of Maxwellian to epithermal flux (assumed to be 1/E), the lower energy limit of the 1/E flux, the energy corresponding to the Maxwellian most probable (modal) velocity and filter thickness. The geometrical configurations were spherical (which on the assumptions madc is equivalent to a beam flux case), cylindrical and slab. By the use of two or three diffe… more
Date: July 27, 1962
Creator: Stoughton, R.W. & Halperin, J.
Partner: UNT Libraries Government Documents Department
open access

Specifications and Fabrication Procedures for Type 3 Fuel Elements

Description: Process and product requirements to be met in the fabrication of Type 3 fuel elements are presented. The fuel elements specified consist of thin plates of a dispersion of highly enriched UO/sub 2/ and ZrB/sub 2/ in a stainless steel matrix which is clad with stainless steel on all surfaces. Quality assurance provisions are discussed. Process and material specifications and packaging and packing for shipment are described. Sample calculations and drawings are included. (M.C.G.)
Date: April 27, 1962
Creator: Edgar, E. C. & Clayton, H. R.
Partner: UNT Libraries Government Documents Department
open access

Temperature Coefficients of the Reactivity Measurement Facility

Description: The temperature coefficient of the Reactivity Measurement Facility was found to be 49 plus or minus 1 mu k/ deg C (1 mu k = 10/sup -6/ DELTA k/k) in the range 15.4 to l7.8 deg C. The change in the net reactivity of a standard sample was --0.48 plus or minus 0.02, --0.66 plus or minus 0.03, and --0.78 plus or minus 0.02 mu k/ deg C in three measuring positions. These low values generally make temperature corrections insignificant. The above results are compared with previous determined values. T… more
Date: July 27, 1962
Creator: Fast, E.
Partner: UNT Libraries Government Documents Department
open access

Effect of a reactor fuel element failure on the Columbia River radionuclide concentrations at Pasco, Washington

Description: The failure of a fuel element cladding in one of the water-cooled plutonium production reactors permits the erosion of irradiated uranium metal by the cooling water which is normally disposed to the Columbia River. Monitoring systems at both the reactors and at their effluent basin outlets to the river continuously monitor these streams, and if major fission-products release occurs the coolant can be held in retention basins. In addition to these monitoring systems, a river monitor is located a… more
Date: December 27, 1962
Creator: Perkins, R.W.
Partner: UNT Libraries Government Documents Department
open access

Aqueous Processing of Thorium Fuels. Part 2

Description: The status of aqueous processing methods for Th fuels is reviewed. A specially designed 320 ton shear was successfully tested for chopping full size simulated Consolidated Edison type unirradiated assemblies into 0.25-1.5 in. lengths. Pieces about 0.5-in. long are preferred since the core pellets are more severely crushed during the chopping operation, and consequently, the rate of core dissolution is enhanced. The Darex (dtlute aqua regia) and Sulfex (4 to 6 M sulfuric acid) processes for diss… more
Date: November 27, 1962
Creator: Blanco, R. E.; Ferris, L. M.; Watson, C. D. & Rainey, R. H.
Partner: UNT Libraries Government Documents Department
open access

FINAL REPORT OF SL-1 RECOVERY OPERATION, MAY 1961 THRU JULY 1962

Description: In May, 1961, it waa determined no renewed nuclear reaction in the SL-1 pressure vessel was possible as long as water was excluded. It was therefore possible to proceed with the final phase of the SL-1 recovery. This work consisted of moving the pressure vessel and core to the Hot Shop at the north end of the National Reactor Testing Station, dissecting and analyzing the reactor and its components, cutting up and burying the reactor building, and decontaminating the rest of the SL-1 area. These… more
Date: July 27, 1962
Partner: UNT Libraries Government Documents Department
open access

THORIUM-MOLYBDENUM PHASE DIAGRAM

Description: The phase diagram of the Th-- Mo alloy system has been determined to be of the eutectic type with a eutectoid reaction associated with the Th alpha-beta transformation. X-ray, thermal, electric resistance, and metallographic methods have established the eutectic point at 1380 plus or minus 10 deg C and 7.0 plus or minus 0.5 wt% Mo. A eutectoid reaction is proposed at 1358 plus or minus 5 deg C and less than 0.1 wt% Mo. No solubility of Th in Mo was detected at 1325 deg C. (auth)
Date: March 27, 1962
Creator: McMasters, O.D.; Palmer, P.E. & Larsen, W.L.
Partner: UNT Libraries Government Documents Department
open access

Effect of CO$sub 2$ on the Strength and Ductility of Type 304 Stainless Steel at Elevated Temperatures

Description: The mechanisms by which the carbon dioxide coolant affects the strength properties of type 304 stainless steel were investigated in the range 1300 to 1700 deg F (704-927 deg C). Creep- and stress-rupture results obtained on sheet materials in wet and dry CO/sub 2/ and argon are compared. The effect of annealing in CO/sub 2/ on the tensile strength and ductility was also investigated. The question of whether the strengthening observed in CO/sub 2/ was due to oxidation or carburization was determ… more
Date: September 27, 1962
Creator: Martin, W. R. & McCoy Jr., H. E.
Partner: UNT Libraries Government Documents Department
open access

Corrosion Mechanism of Zirconium and Its Alloys--Diffusion of Oxygen in Zirconium Dioxide

Description: The diffusion rate of O in anion-deficient zirconia, ZrO/sub 1.994/, was determined by the interface migration of stoichiometric oxide and is represented by the equation D = 0.055 exp (--33,400 surface proces 3100/RT). A comparison was made with other processes that occur in the metal and the oxide. Excellent agreement was noted between activation energies of O diffusion in ZrO/sub 1.944/ and those for parabolic or cubic oxidation in both air and water. It appears that O diffusion in the oxide … more
Date: July 27, 1962
Creator: Douglass, D. L.
Partner: UNT Libraries Government Documents Department
open access

A Method of Solving the Time Dependent Neutron Thermalization Problem

Description: The method of singular eigenfunctions introduced first by Van Kampen and developed later by Case and Mika in connection with a one velocity transport problem, was adapted to solve the time and energy dependent infinite medium problem. The expansion of neutron density and scattering kernel in series of Hermite functions reduces the Boltzmann equation to a system of homogeneous linear equations. The resulting set of regular and singular eigenfunctions is shown to be complete and explicit formulas… more
Date: August 27, 1962
Creator: Koppel, J. U.
Partner: UNT Libraries Government Documents Department
open access

Structure of reactor: part 2 of the Tory II-C program

Description: Declassified 26 Nov 1973. Information on the Tory-2C Reactor is presented concerning the reactor core structure, core supports, fuel assemblies, and control rods. (DCC)
Date: September 27, 1962
Creator: Walter, C.E.
Partner: UNT Libraries Government Documents Department
open access

An Evaluation of Four Processes for Recovering Uranium From Zirconium Fuels at the Idaho Chemical Processing Plant

Description: Four zirconium fuel processes -the present STR process, the modified Zirflex process, the barium fluorzirconate process, and the sodium formate process-were evaluated in detail for technical and economic feasibility. The evaluation was based on installation as the second generation ldaho Chemical Processing Plant zirconium process. Two nonaqueous processes, the ARCO and the fused salt fluoride volatility processes, were included in a preliminary evaluation, but were eliminated on the basis that… more
Date: April 27, 1962
Creator: Burn, P.
Partner: UNT Libraries Government Documents Department
open access

A Study of Modifications for Ornl Liquid Waste System. I. High-Level Storage Tanks and Intermediate-Level Evaporator

Description: As a means of reducing the quantity of radioactivity released to the environment by radioactive liquid waste discharges at ORNL, it is proposed that two 50,000-gal stainless steel storage tanks and a 600 gph stainless steel, submerged-coil evaporator be installed. The tanks, approximately 10 ft in diameter by 85 ft long, will be equipped with cooling coils attached to their outside surfaces for removal of a maximum of 300,000 Btu/hr of decay heat, and will be supported inside a concrete vauit f… more
Date: April 27, 1962
Creator: Weeren, H. O.; Blomeke, J. O. & Stockdale, W. G.
Partner: UNT Libraries Government Documents Department
open access

Design and Construction Features of a Variable Gap Thermionic Converter Tube

Description: Design and construction features are presented for a parallel-plane thermionic converter tube which has an interelectrode gap that may be precisely varied from zero to six inches. (auth) 3Z72 Thermionic diodes and pentodes (with their associated circuitry) were compared as elements in logarithmic current amplifiers. Diodes generally give greater accuracy, but pentodes have simpler associated circuitry and hence may be preferred for certain applications. Logarithmicto-linear transfer characteris… more
Date: September 27, 1962
Creator: Gust, W. H. & McKee, E. S.
Partner: UNT Libraries Government Documents Department
open access

An Integral Design Technique for Wideband Multistage Transistor Amplifiers

Description: A philosophy for designing wideband multistage transistor amplifiers is discussed. The amplifier is visualized as an integral unit, the interstage networks constituting the elements of the amplifier unit. By designing the amplifier as a unit and adjusting the over-all response (gain and bandwidth) with the interstage time constants, an increase in gainbandwidth product is realized over the iteratively designed amplifiers. The resulting increase in gain- bandwidth product results from absence of… more
Date: April 27, 1962
Creator: Scott, L.
Partner: UNT Libraries Government Documents Department
open access

Water Test Development of the Fuel Pump for the MSRE

Description: A vertical centrifugal sump-type pump utilizing commercially available impeller and volute designs was selected to circulate the fuel salt in the Molten Salt Reactor Experiment (MSRE). Tests were conducted in water to determine the adequacy of the pump design, to assist design of the prototype fuel pump, and to investigate the effectiveness of xenon removal with high velocity liquid jets contacting sweep gas in thc pump tank. Hydraulic head characteristics were within +1 to -3 ft of manufacture… more
Date: March 27, 1962
Creator: Smith, P.G.
Partner: UNT Libraries Government Documents Department
open access

Control of information on Columbia River

Description: This brief report (December, 1962) discusses the effect of effluents from the Hanford Production reactors on the water temperature of the Columbia River.
Date: December 27, 1962
Creator: Johnson, W. E.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen