Abstract: "The objectives of this program are the development of zirconium-base alloys possessing exceptionally good corrosion resistance to 680 F water or 750-900 F system and/or improved strength at elevated temperatures. Approximately 100 binary compositions were prepared and screened by corrosion testing in 680 F water; selected compositions were exposed to 750 F steam. The data obtained indicate promising bases for ternary and quaternary alloys. Related investigations involving zirconium purity and heat treatment for improvement of corrosion properties are proceeding. Hydrogen pickup and mechanical properties will be used as acceptability tests on promising compositions."

Abstract: A definitive investigation of the boron-carbon equilibrium system is being made by X-ray diffraction, metallographic, and thermal analytical techniques. On the basis of metallographic and X-ray diffraction studies it is concluded that boron carbide has a range of solubility from approximately 10 to 20 atomic per cent carbon at 1500 degrees to 2000 degrees Celsius. The melting point of the carbide-graphite eutectic has been established as 2325-2350 degrees Celsius. No reversible allotropy of the beta-rhombohedral structure has been observed. The solubility of carbon in boron is very small. The melting point of dilute carbon alloys is found to be essentially the same as that of pure boron (2040 degrees to 2050 degrees). No metallographic evidence of a three-phase reaction of dilute alloys is observed.

This document reports progress during the month of February, 1961, recording investigations and studies of a flow rate using a curved pipe or S-tube and documenting measurements of mass flow, tube design and construction.

Quarterly report describing the progress and development of improved zirconium alloys for service in superheated water and steam. This report covers the period between October 1 to December 31, 1960 and was conducted by the United States and the European Atomic Energy Community (EURATOM).

Abstract; The fission product data obtained during SM-1 Core I operation (June 1957 - May 1960) is reviewed briefly and interpreted. Evidence is presented to indicate that a fuel element defect was responsible for the high fission product activity level observed in the primary coolant. Relative escape coefficients are calculated and the defect size estimated. Anticipated fission product levels during SM-1 Core II and SM-1A Core I operation are estimated from alpha surface contamination data on completed fuel elements. The importance of in-line sampling for monitoring fission product activity is stressed as well as the need for failed fuel element detection methods.

Introduction: This is a final report on the evaluation of Kanigen electroless nickel plating for surfaces in contact with water and steam i a sodium heated AISI Type 316 stainless steel steam generator. The purpose of the coasting was to afford protection from stress corrosion cracking originating on the water-steam side of the unit. It has been concluded that the kanigen coating does not afford adequate protection for the services condition intended. This work was performed as part of the research and development program for the United States Atomic Energy Commission sodium Components Design Project.

Tables of the electron pressure and kinetic energy for a partially degenerate, relativistic, ideal electron gas are computed by numerical integration using an IBM 7090 electronic calculator. These are given in terms of log10(B) and log10(0), where B is the ratio of the temperature to the rest mass of the electron and (O) is proportional to the numerical density of electrons. The tables include values of T from 5 million to 400 billion degrees and cover the range of electron densities from the region of a perfect gas to the region of complete degeneracy.

"This is the third quarterly report on Task II dealing with Methods Development for Radio-Tracing of Coal Product Hydrocarbons With Tritium. The problem of accurate low-level tritium assay for tagged hydrocarbons has been resolved and attention is now primarily directed at the questions of tritium mobility and radio-chemical purity in tagged tracers."

"Mesic decay of hyperfragments is discussed systematically on the basis of a previous model for hyperfragments. The general formalism for the two-body and three-body mesic decay was developed. The polarization-direction correlation and the angular correlation for the two-body and the three-body decays are discussed together with the decay probability. The formalism was developed so as to include the isotopic spin selection rule ( DELTA I = 1/2 and 3/2) for the mesic decays. The theory was applied especially for the low mass number hypergragments where it was found that the branching ratios of the two-body and the three-body mesic decays of /sup 3/H/sub i and /sup 4/H/sub i, (/sup 3/ H/sub i yields /sup 3/He + i/sup -/)/(/sup 3/H/sub i yields D + p+ pi /sup -/) and (/sup 4/H/sub i yields /sup 4/He + pi /sup -/)/(/sup 4/H/ sub i yields /sup 3/H + p + pi /sup -/), could be used for the determination of the spins of both hyperfragments. The fraction of the p-wave decay rate for the free LAMBDA decay obtained from the reaction /sup 5/He/sub i yields /sup 4/He + p + pi where the decay proceeds through two-resonant states (p/sub 3/2/ and p/sub 1/2/) …

"An investigation was made into the various processes for the fixation of mixed fission products as solids in order to determine the extent they could be utilized as heat sources for thermoelectric generators. Generators of up to ten watts can be designed and built with state-of-art'' thermoelectric materials and mixed fission products soon to be available from the ldaho Falls calcination pilot plant. Mixed fission products from other processes and plants to be on stream'' in this decade will be capable of fueling practical generators into the kilowatt range using thermoelectric materials available in the same time period. A survey was made on current research and development efforts on waste fixation processes. Studies showed that a wide range of power densities (from 0.002 to 0.2 watts per cubic centimeter) will be available from calcined fission product wasted. An experimental program for the consolidation of low density, Idaho Chemical Processing Plant alumina type wastes is reviewed. Preliminary results indicated that densification factors of three to four are readily obtainable for such wastes."

The method of dispersion relations has in recent years found a wide application for the study of elementary particle reactions. Most of the work, however, deals with reactions of the type [formula], while the theory of those with more than two particles in the final state is still in a very preliminary stage. One reason for this is that even with only three particles in the final state the theory is already much more complicated. Nevertheless, a further development of the theory seemed to us very desirable. The theory at present is being developed on various levels simultaneously. Generally speaking, the aim of this paper is to put the theory in a form as closely as possible analogous to Mandelstam's formulation of the theory of reactions of type [formula]. In the later sections we specialize on reactions [formula], but as much as possible the formulation is in more general terms.

The radius of a c-p hybrid orbital has been found to be given by the expression: [formula] where A is the radius of the pure p orbital, B, a universal constant equal to 0.336 A, and [ ], the coefficient of mixing in the hybrid s + [ ]. When radii appropriate for the orbitals that are paired together are used, bond length is additive of the orbital radii and no Schomaker-Stevenson correction is necessary. This shows that most bonds can be treated as covalent, single and localized.

The problem of the natural convection of an electrically and thermally conducting fluid within a long, narrow, vertical toroidal channel centered in a large block of an electrically and thermally conducting solid is analyzed. A uniform horizontal magnetic field is applied to the fluid, and the bottom of the solid block is maintained at a higher fixed temperature than the top. The laminar steady-state single-cell convective motion of the fluid is considered and an approximate solution is found for the heat transfer rate between the bottom and top surfaces of the block in the limiting cases of small and large Hartmann number. A numerical example is given for liquid sodium in which the application of a magnetic field of a few hundred gauss is shown to significantly reduce the rate of heat transfer.

An electron can suffer a very large acceleration in passing through the Coulomb field of a nucleus, and in this interaction the radiant energy (photons) lost by the electrons is called bremsstrahlung (also, bremsstrahlung sometimes designates the interaction itself). If an electron whose total energy [formula] traverses matter of atomic number Z, the electron loses energy chiefly by bremsstrahlung. This case is considered here.

The sodium-ammonia solution system permits investigation of an array of compositions spanning the transition from non-metallic to metallic bonding. Reflection spectra in the range 1-20 [ ] were measured for solutions of mole ratio 5.5 to 168 [ ] per Na. The dilute solutions show peaks characteristic of the vibrations of ammonia and a strong peak near 1.5 [ ] which is assigned to the solvated [ ] species. Concentrated solutions show high reflectivity over broad wavelength ranges. The results for nearly saturated solutions are fitted reasonably by the free electron model, but in the range of mole ratio 10-15 a complex array of energy absorption processes of finite frequencies are required to fit the spectra.

Previous attempts to interpret chemical structure in terms of x-electron resonance have been recently criticized. A reinterpretation of the lengths of the C-C bonds in terms of orbital radii has not revealed any effects of x-electron resonance in the ground states of classical molecules such as 1, 3-butadiene, methyl acetylene, etc. Even in a non-classical molecule such as benzene, resonance shortening of the CC bond is only in terms of the strengths of the hybrid orbitals. If the lengths and force constants of the C-C bonds vary with hybridization, so also must their bond energies. If resonance is not important in classical molecules, the heat of atomization of a classical molecule must be given by the sum of either the energies of the bonds or the contributions of the atoms present in it. To test this theory, we have estimated the contributions of some standard carbon atoms, viz., primary, secondary, tertiary, quaternary, trigonal, and diagonal carbon atoms.

This Preliminary Hazards Summary Report has been prepared for submission to the United States Atomic Energy Commission in compliance with Part 50 of the regulations governing the licensing of production or utilization facilities, pursuant to the Atomic Energy Act of 1954, as amended, and contains the general information required by 10 CFR 50.34.

A reference design of a large high power density core has been established representing the available technology as of August, 1960. Reference core performance and cost should improve considerably after incorporation of improvements now under study.

The General Electric Company is proceeding with an irradiation program to proof test a representative array of Savannah I fuel rods. Irradiation of a test assembly containing Savannah I fuel rods has begun and it is proposed that the results of this irradiation will permit an advance evaluation of the fuel performance and fuel burnup in the Savannah I reactor. This report covers the first two quarters of the reporting period. All aspects of the subject program have been consolidated and applicable portions are discussed in some detail.

Equipment and techniques for remote examination of irradiated fuel assemblies applicable to the Maritime Program are described. The following subjects are covered: visual and photographic examination, dimensional measurements, gamma activity scanning, fission gas release and fuel rod void volume determinations, density measurements, metallographic examination, and radiochemical burnup analysis.

The experimental demonstration of fission product release from over heated reactor fuel is necessarily subject in many respects to the arbitrary conditions imposed by the experimenter. Since an almost infinite latitude exists in the choice of materials, atmospheres, gas, velocities, temperatures etc., some allowance for an extrapolation to alternate conditions is definitely in order. The conditions imposed in this study are best described as those most likely to maximize fission product release. Two of the most important variables not investigated in the present report are the influence of metal cladding and the difference in internal nuclear heating as opposed to external radiant heating. In addition a significant uncertainty exists in the understanding of diffusion through large masses such as might result from a scaled-up melt down in a reactor.

The general solution to the basic differential equation d^4w/dy^4 +4w= -4f(y) is transformed from the primary form treated in most texts to an alternate form in which each integration constant corresponds to one edge condition at y=0. The relationships between the integration constants of the two forms are derived and the values for the transformed functions are tabulated. The particular solution is derived in general and given in unique form for various functional forms of f(y). Matrix notation is used throughout the derivations; however, a knowledge of matrix theory is not need for application of the results.

Preliminary results from experiments on the dissolution of beryllium metal and sintered UO2-BeO fuel pellets are reported. In all cases the pellets were fired in hydrogen at 1650-1800°C. Uranium, from UO2-BeO pellets containing more than 60% UO2, is readily leached with boiling 6-13 M HNO3 in about 6 hr. The BeO in these pellets dissolves only slowly in nitric acid; however, in 8 M HNO3-0.2M NaF, it dissolves at about the same rate as the UO2. Sintered pellets containing less than 10% UO2 do not dissolve rapidly in common aqueous reagents. The highest rates are obtained in boiling acidic fluoride solutions; e.g., sintered BeO and BeO-8% UO2 are dissolved initially at a rate of about 1.7 mg min-1cm-2 (13 mils/hr) in boiling 5.8 M NH4HF2.

A program translates an algebraic language like Algol into the machine language of an electronic computer must perform the following functions.