This report is categorized in four categories: (I) Power as Commander-in-Chief, (II) Power to appoint and receive Ambassadors,(III) Power by and with the consent of the Senate to make Treaties and (IV) Power as chief Executive.

I have understood my assignment as a review of some of the work done in high-energy physics with polarized proton targets and a description of some of the special problems connected with polarized targets. Most of my report will be based on the polarized target that I am most familiar with--that constructed by Jeffries, Schultz, Shapiro, and myself. This target is no longer unique; in fact, it is now somewhat old-fashioned in some respects. Other polarized proton targets are in operation at CERN, Saclay, the Rutherford Laboratory, Argonne National Laboratory, the Soviet Union, and there is a target newly in operation at the Brookhaven Laboratory. Other targets are in operation or are in the process of design or construction at a number of other places. Unfortunately, none of these targets consists of pure hydrogen. The target material most often used is made of lanthanum magnesium nitrate, LMN. About a quarter of the weight of this crystal is water; it is the protons within the water molecules that are polarized. Hydrogen constitutes only 3 percent of the weight of the crystal. This means that scattering processes on hydrogen must be distinguished kinematically from scattering processes involving the heavy elements of the …

The capacity of photosynthetic organisms to exhibit photo-induced electron paramagnetic resonance (EPR) signals has been known for over ten years. Subcellular units of photosynthetic materials, the quantasomes and the chromatophores, are capable of Hill Reaction activity, and also of exhibiting the light-induced EPR signals. This, coupled with the rapid rise and decay kinetics of these signals, suggests but does not prove that the unpaired electrons are involved in the initial electron transfer processes in the primary quantum conversion act. The identification of the species giving rise to these signals and their connection with processes of primary quantum conversion remains elusive even though such varied approaches as mutant strains, special growth conditions, extreme physical conditions, special metabolic inhibitors, etc. have been applied to this problem. In this communication the authors wish to report another method being used in an attempt to identify the species responsible for the unpaired electrons. Hoffman prepared a water soluble, stable free radical, di-tertiary-butylnitroxide (hereafter called DTBN), which is a 'vigorous free radical scavenger'. It shows a sharp, well resolved, symmetrical, three-line paramagnetic resonance spectrum that is relatively insensitive to the molecular environment. The chemistry of di-tertiary butylnitroxide has not been studied extensively. However, four distinct types …

From abstract: "This report describes and evaluates the variables affecting contamination of precise devices...In the present report these variables are discussed in more detail and the basis for their inclusion in the listing are given. The relative importance of the several parameters will be discussed in another report."

Introduction: The U.S. Geological Survey is appraising the possibility, however slight, that the ground water beneath the Nevada Test Site, possibly contaminated by nuclear detonations, may carry radioactive fission products to places where they may constitute a public hazard.

The Irradiated Rupture Prototype (IRP) has been used for rupture testing irradiated NPR prototype fuel elements. Most of the tests have been made to determine the rupture effect of different reactor exposures, fuel element geometries and water cooldown rates following the start of the rupture. This report summarizes the results obtained to date, mentions where information is lacking and gives further tests scheduled for the IRP.

An evaluation of particle dispersion from natural and artificial sources has been made relating this information to circulation processes in the mesosphere, stratosphere, and troposphere. The data on natural particle and nuclear debris dispersion have been interpreted in terms of their significance in regard to SNAP fuel reentry dispersion and extended by various fall-out time and dispersion calculations.

This document details activities of the N-Reactor Department during the month of February 1964.

This report itemizes the irradiations performed by Testing and Irradiation Services for Battelle-Northwest. It lists the material being awaiting disposition and material shipped during the report period. Information consists of: TISR No.; request number; target material; piece number; operating time; CMK absorbed; charge date; location; exposure to date-NVT; discharge, date and time; and shipping date.

This report details activities of the N-Reactor Department during the month of August 1963.

This report itemizes the irradiations performed by Testing and Irradiation Services for Battelle-Northwest. It lists the material being irradiated, awaiting disposition and material shipped during the report period. Data are given in table form. An explanation of the various columns in the report is given.

Target elements were designed and built to fit into 1.25% U{sup 235} driver elements. These targets had an aluminum -- 0.583% lithium alloy core enriched to 63.5% in Li. The targets had a coextruded aluminum jacket as a tritium barrier and a Zircaloy jacket as a corrosion barrier to the 300 C reactor water.

During April 1962, equipment in both the main Redox Building (202-S) and the Plutonium Concentration Building (233-S) vas rearranged to allow the accumulation and recovery of neptunium without interference with the production of uranium and plutonium. In order to do this, the former rework column (1S) was put into continuous service as a neptunium recovery column, the Third Plutonium Cycle was converted to a neptunium decontamination cycle, and ion-exchange equipment was installed in the 233-S Building to replace the Third Plutonium Cycle. The neptunium, once decontaminated, will be concentrated and loaded out via its own system in the 233-S Building. To check the critical mass safety of the new arrangement, a formal hazards review was made, the results of which are reported in this document.

This document summarizes the requested study of theoretical factors influencing the expected conversion ratio of the fringe enrichment portion of an E-N loading. Exact calculation of the quantity is very complicated and will not be attempted here; however, it is possible, with simple geometric approximations, to derive relative conversion ratios. This present report summarizes the results of a study incorporating actual operating data from the present poisoned top and unpoisoned bottom fringe loadings at H Reactor. There is calculated decrease in buckled-zone (E-metal blanket) conversion ratio of 13% in the E-N loading as compared to normal fringe loadings; this loss is due to the effective reduction in pile size due to the presence of the blanket of BOLL material in the outermost lattice unit and the accompanying increase in enrichment demands. On a full pile basis, this loss represents about 5%. However, on the assumption that an atom of tritium is equivalent in value to an atom of plutonium, the BOLL material in the outermost layer augments over-all pile conversion by about 4% in the green reactor, and probably more in the ripe reactor in addition to compensating the 5% loss in the E-metal blanket. An Appendix is included as …

The purpose of this test is to obtain data concerning the reactivity effect of horizontal control rods in the E-N loading at H Reactor. The accurate calibration of the control rods will then provide more accurate measurement of the other reactivity variables associated with the E-N loading.

Object of this paper is to present preliminary results of experiments in Hanford in-reactor loops to determine if exposure to neutrons will increase corrosion rates of Al alloys, Zy-2, and 304 stainless steel. Results were negligible or no corrosion.

The report is divided into: Present reactor fuel production, N-RD production fuels, N-fuel development, and current reactor fuel development.

Goal exposure and power level planning and administration on either a short-term or long-term basis, is heavily dependent upon assessment of the level of metal performance. It is the purpose of this document to present a method of monitoring the metal performance level employing the concept of control charts, and to propose adoption of this method as the basis for detecting changes in the metal performance level of the three main types of production fuel elements, i.e., C-II-N, O-II-N, and K-III-N material. Supplemented with predetermined decision rules for evaluating the extent to which the metal performance level has improved or declined, these control charts become valuable tools for use in making IPD operating decisions.

This document lists all tanks which were active during each month by Waste Farm, which includes all tanks to which additions or subtractions were made. Each type of waste was indicated in each case, along with the nature of transfer and any pertinent remarks. Also reported are gallonage and inches of liquid in each tank.

This document defines the objectives, bases, and functional requirements that shall govern the preparation of design of the coolant backup system for the three remaining smaller reactors. This project will increase the reliability of the coolant backup facility at B Area by providing an independent last-ditch coolant system to B and C Reactors. The reliability of the last-ditch system for D Reactor will also be improved in that the present F and H leg of the export system will no longer be a part of the new export system. The objective of this document is to define the operational and technical requirements of the new facility and to describe the functional requirements of the proposed coolant backup system for the purpose of design.

The objective of this production test is to evaluate the irradiation behavior of N Reactor fuel elements at conditions equivalent to or more severe than those expected in N Reactor. N Reactor fuel elements are authorized for irradiation in KER Loops 3 and 4 to exposures no greater than 3000 MWD/T. Tubular steel spacers, per steel spacers, solid steel dummies, and a flow channel temperature measuring thermocouple train are authorized for use in KER loops 3 and 4 to permit positioning the fuel element charge in the process tube, controlling pressure drop across the process tube when using short fuel charges, and measuring the coolant temperature unbalance in the different fuel element flow channels.

This report provides the experimental results of uranium chemical machining tests.

The current-revision of the Process Optimization Program contains two empirical plutonium-exposure expressions. One relates total Pu conversion to exposure and the other, Pu-240 buildup to exposure. The former was incorporated to save computer time and the latter to provide product quality data. Both of these relationships, in addition to a third which relates Pu-241 buildup to exposure, are used in PULP-3, the data generator for LP-90. EMCON-3, a 7090 computer program which determines arbitrary constants for all three empirical expressions, has been devised. It uses, as input, official conversion data and will facilitate rapid evaluation of the effect, of periodic revisions in official conversion data, changes in reactor loadings, and/or changes in product specification. This document contains a discussion of the empirical expressions, the program mechanics, and program input/output. A Fortran listing of the program logic a deck assembly diagram, and sample program output are included in the appendix to aid the reader in using and/or revising the program.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Crawford Martin, regarding a legal question submitted for clarification;Constitutionality of H.B.1187,60th Legislature,Regular Session 1967.