This technical report reviews the general purposes and immediate goals of the Heat Transfer Group at BNL's study of the heat transfer characteristics of alkali metals with phase change in forced convective flow. This report also presents a brief description of the design and development of the test loop. Figures detailing findings accompany the report.

Foreword: This report describes the results of a series of engineering evaluation studies conducted between July 1, 1961 and June 30, 1962, related to heavy water moderated power reactor plants.

Report describing a study which analyzed thermal characteristics of Type 3 elements planned for installation in the SM-1, SM-1A and PM-2A plants, for both steady state and loss of flow transient conditions. Results of this analysis for steady state conditions indicate that the SM-1, SM-1A and PM-2A Type 3 cores will operate safely at design and scram conditions.

Abstract: This preliminary technical report covers design of the SM Type 3 element, its use .in.. SM-1 Core III, and planned use in the Type 3 Core for PM-2A. The Type:3 element characteristics are compared with Type 1 (SM-1 Core I) element nuclear, metallurgical, thermal and hydraulic characteristics and fabrication. The effect of using the Type 3 element in SM-1 Core III and. its planned use in a Type 3 Core for PM-2A is discussed with regard to operation, shielding, reactor safety and all conceivable special problems.

"A linearized three component MHD theory is given. The three components are two oppositely charged species and a neutral species. Linearized macroscopic equations are presented which in the limit of vanishing magnet field reduce to fluid dynamical equations, and in the limit of vanishing neutral components is frictional. In addition the sound speed that enters is a function of three equilibrium densities. These equations yield a dispersion relation which is tenth order in the wave speed. The decay frequencies of all ten modes are calculated to first order terms in the friction, and are found to be all isotropic."

"A series of high urania-content glasses were fiberized and examined for high-temperature strength properties. One glass, RX360 containing 60% U/sub 3/O/ sub 8/ by weight, had better high-temperature tensile properties than any glass previously reported. It was observed that many of the glasses studied separated into immiscible phases and that the fiberizable glass phase had lower U/sub 3/O/ sub 8/ content than the base compositions. A physical analysis of crystal structures of the devitrification products from the nuclear fuel glasses indicated that most of the crystals consisted of uranium oxide in a reduced state. By adding O/sub 2/ to molten glass, it was possible to eliminate most of this devitrification. By elimination of crystals, the fiberizing of the glass was more uniform and the glasses produced had more consistent physical properties."

Abstract: This technical report contains a comprehensive analysis of the nuclear characteristics of the SM-1 Core I. Comparison of analytical and experimental results for neutron ages and core reactivities of a variety of cases investigated shows that the MUFT III with P-1 slowing down approximation gives the best results. At startup the core reactivity and rod bank worth under various operating conditions are investigated and compared to experiment. Core lifetime was calculated to be 16.8 MWYR compared to 16.4 MWYR experimental. The temperature coefficient has been calculated and compared to experiment as function of burnup. In Appendix A, flux distribution, temperature coefficient, effective delayed neutron fraction and core life are analyzed by Dr. R. L. Murray by one and two group modified theory series expansion calculations.

A report regarding proceedings of the nuclear superheat meeting no. 6, held March 7, 8 and 9, 1962, in Windsor, Connecticut.

From abstract: A preliminary study has been made of a direct access, streamlined process for the rapid fabrication of fuel using uranium-233.

Abstract: This technical report covers the zero power experiments performed on PM-2A Core II at the Alco Critical Facility. PM-2A Core II is the first replacement core for a portable pressurized reactor at Camp Century, Greenland. Core II is the same as Core I with the exception that Core II has an increased burnable poison (B-10) content. The zero power experiment consisted of fuel element uniformity test; core assembly test, development of an on-site loading procedure and an analysis of experimental data. Physical characteristics determined include distribution of fuel and B-10 in the fuel plates, minimum critical mass, control rod bank calibration, and integral rod worth. The report concludes with an analysis of the experimental data including estimated uniform and non-uniform burnup rates.

From abstract: Results are reported of a study to determine the most economical method of utilizing nuclear heat to gasify a North Dakota lignite and a West Virginia bituminous coal so that the resulting gas is suitable as a source of synthesis gas for fuels and chemicals.