Report discussing progress from May, 1960 through July, 1960 on a study of radiation synthesis involving halogenated compounds. Experimental procedures and data are included.

The following document describes the usage of the LRL 9-ZOOM code, a neutron diffusion theory reactor code for the IBM 709. The code has been modified to solve configuration of a series of stacked cylindrical disks, designating a new geometry case.

Scope. This specification covers ingots of zirconium alloy designated as Zircaloy-2, and intended for the production of reactor components.

Scope. This specification covers Zircaloy-2 wire material for reactor use where high integrity and satisfactory corrosion resistance at elevated temperatures are required.

Scope. This specification covers Zircaloy-2 tubing, both seamless and welded, for reactor fuel rod sheathing where high integrity, and satisfactory corrosion resistance at elevated temperatures ae required.

Scope. This specification covers Zircalogy-2 sheet and strip material for reactor use where high integrity and satisfactory corrosion resistance at elevated temperatures are quired.

Abstract. The Equivalence Theorem of P. Lax is extended to difference schemes for initial-value problems for linear inhomogeneous PDE with linear inhomogeneous boundary values and for boundary-value problems.

The purpose of Project Cowboy was to investigate the seismic signals generated by chemical explosions in underground cavities, with particular emphasis on the possibility of decoupling of these signals from the surrounding media. The project site was the Carey Salt Company salt mine, located approximately five miles west of Winnfield, Louisiana. The tests were run during fiscal year 1960. This report presents the results of tests performed on specimens from the samples of salt taken in the area.

The wide use of liquid oxygen as an oxidant in rocket engines has resulted in an increased interest in low-temperature heat transfer. Storage tanks for this type of application, being uninsulated, contain a boiling-liquid low-temperature sink, which is susceptible to environmental heat inputs and subsequent liquid loss by vaporization. Such losses are difficult to predict due to the complex combination of ambient conditions which exist, and the lack of knowledge concerning their combined effects. Heat transfer in this field is difficult to analyze primarily because of its transient nature. This is a result of such factors as: (1) the growth of an insulating frost layer on the outer surface of the container, with its accompanying energy transfer to the system; (2) the temperature dependent convective air pattern that surrounds the container, (3) the transfer of radiant energy to the system, and (4) the mechanical failure of the frost itself with subsequent sloughing from the container wall. A lack of knowledge regarding the coefficient of diffusion of water vapor through air and the thermal conductivity of frost in this depressed temperature range further complicates the predictions of heat transfer.

This paper describes the measurement of control rod strength in the PCTR. The first section outlines the theory and method of such a measurement, and the second section presents the results of the measurement of the Experimental Gas Cooled Reactor (EGCR) control rod strength. The reactor parameter actually inferred is the difference in the infinitive multiplication factor for a control rod supercell with and without the control rod in place in the supercell. These measurements are, therefore, very closely related to the measurement of k∞ for an ordinary lattice cell.

This document authorizes the performance in accordance with the specifications noted, the PRTR Critical Tests described herein. The experiments described have the following objectives:

This report describes the critical experiments with pin-type oxide fuel elements for the Consolidated Edison Thorium Reactor (CETR). This report also describes the measurements and gives a brief interpretation of the results in some cases

The nuclear characteristics of the CETR are described. Core operating lifetime, control-rod worth, and power density distribution are discussed in relation to maximizing the core operating life. Other objectives of nuclear design are to minimize the power-density variation and to assure control of the reactor.

The design functions and fabrication details for internal components of the CETR are presented and pertinent analytical stress studies are summarized. Functions of the internal components include proper orientation and support for the fuel elements, proper distribution of primary coolant within the reactor vessel, and the establishment of guide channels for the control rods.

The series of experiments described in this paper was performed to determine reactivity values of various patterns of fully inserted cruciform control blades. The experiments yielded the worth of fully inserted blade patterns in terms of their holddown characteristics.

A technique for measuring extremely small temperature changes by means of a pyroelectric device is described. The sensing element is a short thin rod of polarized barium titanate ceramic with electrodes on the ends. The electric charges produced by changes in temperature are measured by a vibrating-reed electrometer. A number of calorimetric and noncalorimetric applications for the device are suggested.

This development work was undertaken to investigate and standardize scintillation detector and transistorized circuitry techniques in instruments used for detecting and measuring alpha and beta particles, gamma photons, and both slow and fast neutrons. At the present time, the standard radiation detection instrumentation used at Hanford employ vacuum-tube circuitry with typical detectors being ion chambers, G-M tubes, HF3 tubes, etc. The vacuum tubes require excessive battery power, and some of the circuits are adversely affected by humidity and temperature conditions.

Scope. This specification covers ingots of zirconium alloy designated as Zircaloy-4, and intended for the production of reactor components.

Scope. This specification covers Zircaloy-4 wire material for reactor use where high integrity and satisfactory corrosion resistance at elevated temperatures are required.

Scope. This specification covers Zircaloy-4 sheet and strip material for reactor use where high integrity and satisfactory corrosion resistance at elevated temperatures are required.

Abstract. The idea of determining potentials from phase shifts is here called the "optical model" while the construction of an effective single particle scattering potential from the known two-body forces is called the "optical potential." A novel method is given for construction of the optical potential with the Pauli principle and its difficulties are pointed out. In the Appendix one connection between the optical potential and optical model is given.

Abstract. The measured stresses and deflections of cylindrical shells with free ends, when subjected to concentrated loads along the central diameter, are presented. An empirical analog is made with a simply supported flat plate for which stresses and deflection are easy to compute. Over the range of parameters studied (ratio of cylinder diameter to wall thickness varied from 32 to 64, ratio of cylinder length to diameter varied for. 0.6 to 5) the agreement is such that the empirical results should have useful application in the design of shells for local loading.

At the Montreal colloquium Ahmed urged Oliver to make batches of emulsion which would differ only in gelatin concentration. At that meeting Oliver had reported finding a correlation between grain size and silver ion concentration during precipitation, as implied by Perfilov and his Leningrad colleagues. Ahmad felt that one should have more precise knowledge of the relative influence of gelatin concentration of grain sized and their distribution. The incentive is that, in spite of excellent progress in many laboratories and in consistently dependable production from industry (to us, of course, Ilford is most familiar), nuclear emulsions are needed in a wider variety of sensitivities and grain sizes. Available nuclear emulsions have limitations in sensitivity, discriminatory ability, and concentration of hydrogen nuclei. Fine grain size enhances discriminatory ability. An incentive is also in that there is a shortage of literature dealing with the processes involved in the fundamental steps of emulsion production.

This bibliography is selective, unclassified, and covers the period 1950 - April 1960. Sources consulted were the following: Applied Science and Technology Index (Industrial Arts Index), Chemical Abstracts, Engineering Index, U.S. Atomic Energy Commission Nuclear Science Abstract, Armed Services Technical Information Agency Title Announcement Bulletin, and Publisher's Catalogs.