The so-called Fluoride Volatility Processes refer to several proposed non-aqueous methods of processing irradiated fuel elements. In each of these methods, the uranium is fluorinated to UF6 and then decontaminated by distillation. One of those methods, involving the direct fluorination of the uranium by bromine trifluoride (BTF), has been under investigation at BNL since 1950. In 1952, it was demonstrated at BNL that uranium, as UF6, could be satisfactorily decontaminated by distillation in small-scale pilot plant equipment; end in 1953, BNL undertook the job of determining the technical feasibility of a continuous dissolver on a pilot-plant scale. The reason for the project was that the economic superiority of the process seemed to depend upon its amenability to continuous operation.

From abstract: "Adsorption of radioactive zirconium-niobium from uranyl nitrate solutions by silica gel was increased by increasing the temperature and time the solution contacts silica gel, and decreased by "aging" the solutions before contacting the silica gel."

"Expressions are found to relate DELTA gamma to the n-errors.'' It is demonstrated that the integral n-value concept'' is of no use in the present case. A modification of integrated n-value'' is suggested."

A fused fluoride process for dissolution of zirconium-uranium fuel alloys is being developed. The alloy is dissolved in an equimolar sodium fluoride-zirconium fluoride melt at 600°C by sparging the system with hydrogen fluoride. The uranium is volatilized from the melt as the hexafluoride by a sparging operation with fluorine or bromine pentafluoride vapor. This product is then decontaminated and purified by fractional distillation.

The following report studies an intermediate solid-fuel reactor system for aircraft propulsion.

An estimate has been made of the critical fuel concentration in the HRT, taking into account the effect of the core corrosion sample assembly. The estimate is based on a number of previous calculations of critical concentration in an un-poisoned reactor and one calculation of critical concentration as a function of poison level. The makeup of the first core corrosion sample assembly was used in calculating equivalent neutron poisoning effects. Figure 1 shows the estimated critical concentration as a function of temperature with the corrosion sample assembly in place. At 280°C, the assembly raises the critical concentration by 0.6 g U-235/kg D2O. This effect is equivalent to a uniformly distributed poison equal to 4.1% of the fission cross section. The equivalent poison is greater at lower temperatures, where the uranium concentration is lower.

Abstract: "Theoretical differential cross-sections computed from the optical model for 7 Mev neutrons are presented for a large number of nuclei. The parameters used for the calculations were selected on the basis of best fit to existing experimental data."

Abstract: "Theoretical differential cross-sections computed from the optical model for 14 Mev neutrons are presented for a large number of nuclei. The parameters used for the calculations were selected on the basis of best fit to existing experimental data."

From introduction: "On February 1, 1956, Batelle was awarded a contract by the Army Reactor Branch (ARB) to select, develop, and test core materials which could be used successfully in conducting a Gas Cooled Reactor Experiment (GCRE). The prime objective of the GCRE would be to evaluate small portable reactor systems for military application...The present report is concerned with the GCRE activities at Batelle during approximately the 7 months' period following the first report of this series, BMI-1133. It is primarily concerned with a detailed evaluation of the reference materials as well as of the impact of one material upon the other."

This report follows the radiochemical study of fission and spallation products produced by bombardment of U-235 with 18- to 16-Mev helium ions and of the spallation products produced by 8- to 23-Mev deuteron bombardments of Np-237.

The following report is based off of one of the author's lectures on the physics of plasma, or ionized gases, which was given on July 16, 1954.

From abstract: "Wrought uranium plate, clad in 1100 aluminum with a nickel bonding layer, was irradiated to a maximum exposure of 1600 MWD/T in the MTR and was demonstrated to be suitable as a fuel element material. Beta-transformed plate, or beta-transformed plate that was cold stretched 2-1/4 per cent, did not change appreciably in dimensions but roughened on the surface. As-rolled plate increased in length, but did not roughen. Irradiation reduced the strength and virtually eliminated the ductility of the plate. Abrasion of the cladding caused corrosion pitting. The strength of the nickel diffusion bond between core and cladding was unimpaired by the irradiation."

A monthly report summarizing work perform by Babcock & Wilcox personnel for the U.S. Atomic Energy Commission. In this months report includes specifications a utility loop, further calculations for fuel rods, drawings were reviewed and specifications for the core reactor were reviewed.

"The following is an alphabetical listing of terms and units in common usage at HAPO. Other terms and definitions may be added as the need becomes apparent or as revisions or additional terms are issued by the NCRP and ICRP."

"An account is given of an extensive study of the A-2 Compiler System for the Remington Rand Univac digital computer. In particular, the following topics are discussed: application and performance of subroutines, segmenting, and introduction of subroutines to the library."

Various nuclear characteristics of two-region spherical homogeneous reactors have been computed in order to provide information for the design of HRE-3. Equilibrium isotope concentrations were established using an ORACLE code, and a two-group model was used to obtain critical concentrations and flux distributions. Breeding ratio is plotted as a function of reactor size, blanket thorium concentration, and other design and operating parameters, and the time required for a demonstration breeding is discussed. Tables of results, including neutron balances, are given for selected reactors. a number or relations are presented for estimating the effects of fission products, copper, corrosion products, H2O, and the core tank on breeding ratio.

Abstract: "With magnetic alpha-particle and electron high-resolution spectrographs and scintillation gamma-ray spectrometers, a study was made of the nuclear decay of a number of members of the actinium family - U-235, Th-227, Ra-223, Em-219, Po-215, and Bi-211. Decay schemes are presented for each of these nuclides, together with such correlations as are possible with present theoretical nuclear models. The decay scheme of U-235 and a portion of that of Th-227 are interpretable in terms of the collective model and a spherical shell-model characteristics; however, the intermediate nuclides present complexities not well understood."

This report follows the studies on the interactions of antiproton with ordinary matter.

A report discussing the angular correlation and polarization effects in the production and subsequent decay of particles, particularly those of spin 1/2 and spin 3/2.

It is proposed to reduce the initial wall hangup and consequent plasma contamination of a stabilized pinched discharge by reducing the Bz pressure difference across the current sheath to nearly zero at early times. Two methods for accomplishing this are proposed, both involving multistage programming of the Bz system.

The gamma dose rate in the motor region of the HRT fuel circulation pump was measured with the pump scroll full of radioactive solution. Extrapolation of the data to the solution activity expected in the pump under normal operation gives a dose rate well below that which would result in excessive gas production in the stator can within the life of the pump. The above dose rate does not include the effects of fast neutrons from the fuel solution or of the general cell radiation level in the vicinity of the pump. It appears that the possibility of gas production in the stator from the cell background radiation is sufficiently great to warrant the installation of a shield around the outside of the motor end of the fuel circulating pump.

From abstract: "Radioactive contamination was confined and controlled in an isolation tank when irradiated plates of natural uranium were cut under water."

Experiments in the controlled melting of irradiated fuel specimens, particularly of the APPR, STR, and MTR types have confirmed that prolonged heating in air at temperatures in excess of the melting point results in the release of a large portion of the radioactivity. On the other hand, a moderate amount of heating in air or steam sufficient only to melt a specimen results mainly in the partial volatilization of the rare gases; the halogens, iodine and bromine; and the alkali metals, cesium and rubidium. In the presence of air or water vapor, strontium and other fission products are not released. At trace concentration of fission products, slow melting of the APPR plate at 1525 C in air or steam effected the release of 50 percent of the rare gases, 33 percent of the iodine, 9 percent of the cesium and traces of strontium. After 25% burn-up, the cesium value increased to about 60 percent. Aluminum alloy of the MTR type, also at trace concentration, upon melting at 700 C released up to 2 percent of the iodine, 10 percent of the rare gases, and negligible portions of other fission products. Zirconium alloy of the STR type after 15 percent burn …