Experiment to study temperature conditions during a five-minute heating cycle in the annealing of uranium sheets used as fissile material.

Introduction: The Texas A. and M. Activation Analysis Research Laboratory has been studying the basic technology of activation analysis and its applications since 1958, under the spondorship of the Division of Isotopes Development, U. S. Atomic Energy Commission, and more recently, the National Aeronautics and Space Administration. The information presented in this report summarizes the progress which has been made in these efforts during the period from May 1, 1961, to October 31, 1962.

Introduction: From the inception of the effort to utilize atomic energy Perú has been of interest as a possible source of radioactive raw materials because of its great variety and abundance of metals. Because of this and a desire at that time to develop additional supplies of uranium, a cooperative program to search for uranium deposits was initiated in 1953 by the Junta and the USAEC.

Abstract: This report presents an analysis of coolant boiling in sodium graphite reactors.

Abstract: Perforated BeO plates were thermal shock tested to evaluate the effect of: (1) localized temperature variations adjacent to the perforations, and (2) radial gradients across the entire plate.

Summary report of final hazards for the Boiling Nuclear Superheater (BONUS) Power Station with illustrations.

This report summarizes the results and conclusions of a study made to evaluate the merits of using zirconium hydride as a solid moderator in an integral boiling water-nuclear superheat reactor of the pressure vessel type.

"Uranium and zirconium were bonded by melting the two metals in contact with one another in a bimetallic casting process. Tensile tests of specimens containing the original zone of interface between the two metals showed that all failures were at locations other than the interface. The coefficients obtained for diffusion between molten uranium and molten zirconium varied from 2.13 cm squared per day at 3,380 degrees F. to 9.17 cm squared per day at 3,510 degrees F. the activation energy for the diffusion process was calculated to be 182,000 calories per gram mole."

Abstract: This technical report evaluates hazards involved with SM- 1 plant response and system performance tests (Task XII), to determine the response of the SM-1 plant to step electrical and steam load changes. The report describes the changes in plant equipment and operating procedures for this task and evaluates these changes for possible additional hazards to those described in APAE No. 2, Revision 1, "Hazards Summary Report for the Army Package Power Reactor SM-1."

Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.

Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.

Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.

The objective of the Accurate Nuclear Fuel Burnup Analyses program is to develop more accurate methods for burnup analysis for general use than the current method of analysis of Ca-137 or Sr-90. The program will require from three to five years of effort.

The objective of the Accurate Nuclear Fuel Burnup Analyses program is to develop more accurate methods for burnup analysis for general use than the current method of analysis of Ca-137 or Sr-90. The program will require from three to five years of effort.

Study of the effects on Zircaloy-2 radiation corrosion of a high concentration of excess H2SO4 in a uranyl sulfate test solution using an in-pile loop experiment.

"We will consider two finite difference schemes for the solution of the Navier-Stokes equations in one space dimension. The first is a method used by Lax and Wendroff. The second method is based on an approximate solution of the centered, implicit difference equations. Since this approximate solution is obtained by successive substitutions, we will refer to this second method as an iterative method."