From Introduction: "One part of this study, which is presented in this Monograph, consists of an analysis of electric energy usage and electric power demand data obtained from a sample group of occupied houses at Little Rock Air Force Base in Arkansas, equipped with heat pumps, water heaters, cooking ranges, clothes dryers, and miscellaneous appliances all operated by electricity."

Efforts have been made to experimentally evaluate and to calculate the effect of reactor environment on splines. This report follows some of these efforts and relates them to operational experience. The use of splines in the Hanford Reactors has improved the efficiency and ease of operating the reactors. With the widespread use of splines, it is important to know the effect of reactor exposure to safely and efficiently use the splines in reactor operation.

The N-Reactor Hazard Summary Report examines the hazard from operating the N-Reactor with a uniform fuel loading enriched to 0.947% U{sup 235}. Incentives have been developed for reactor testing of a block of 49 tubes loaded with co-producer elements, i.e. elements capable of producing both weapons grade plutonium and tritium. The element utilizes an outer fuel tube enriched to 1.25% U{sup 235} with an inner target lithium-aluminum rod. Criteria have been developed to guide the evaluation of safety aspects of such tests. It is the purpose of this document to review the hazards associated with the proposed test and to set forth special precautions which will be necessary to maintain a high level of safety.

Research covers the work done on a bench test of an unclad thermionic converter. The objective is to produce an efficient, high-power-density, long- life thermionic power converter using a uranium-zirconium-carbide emitter and a high-temperature nickel collector. (auth)

Abstract: The purpose of this report is to describe the problems inherent to general dielectric strength measurements, and to act as a guide in establishing a method for pulse dielectric strength measurements.

9 > ? ( ing schedule included MTR, ETR, and other aluminum-type fuels that were processed through the TBP headend at 75 to 100% of flowsheet rates and through the Hexone second and third cycle extraction system at up to l5O% of flowsheet values, achieving an over-all recovery of 99.60%. In carrying out basic studies on aqueous zirconium processing, results obtained during the potentiometric titration of zirconium-fluoride-nitric acid solutions with sodium hydroxide were explained by a mechanism in which the untitrated zirconium fluoride species is converted to a fluozirconate and further hydrolysis proceeds via a fluozirconate route. A modified Zirflex flowsheet for processing 2.5% U-Zr alloy fuels is proposed as a result of bench scale dissolution studies on unirradiated PWR plates that showed that dissolver solutions could be stabilized by adding aluminum nitrate and nitric acid. that higher ammonium fluoride concentrations increased the dissolution rate, that higher hydrogen peroxide concentrations lowered the dissolution rate and decreased solution stability, and that ammonia removal by boiling with or without air sparging had little effect on the reaction. Density curves for Zirflex solutions are reported. First tests of the pilot plant for continuous dissolution of zirconium-type elements have indicated that the dissolution rate …

The following report is part of a series of quarterly reports discussing investigations on the development of zirconium-base alloys having corrosion resistance and strength superior to Zircaloy-2 and/or development of materials of equivalent corrosion resistance by exhibiting enhanced strength. This report covers the period between May 29 and June 18 of 1958, made by the United States and the European Atomic Energy Community (EURATOM).

The objective of this report is to summarize all in-reactor operating data associated with PT-288-A. This document will serve as a ready reference to the irradiation history of the fuel elements, and will record any anomalies encountered in the performance of this test.

The loop was charged October 30, 1959 with seven 12-inch Natural Uranium Zircaloy-2 clad 7-rod clusters. The test was primarily for the new hot-headed method of end closure used on these elements. The loop was pressure tested at 4000 psi after it was charged. Initially the loop was held at low-temperature to study the buildup of oxygen (presumably from radiolytic decomposition of water). After startup the neutron activity held at slightly above normal but the strainer gamma activity was exceptionally low. Frequent additions of LiOH bombs were necessary to maintain the pH at 10.0 (previously it was 4--5 pH but was raised to pH 10 for this test.) After the temperature was raised to operating conditions the pH held nicely at 10. On November 16, 1959, the heat exchanger exit temperature thermocouple blew out resulting in depressurization of the loop and a reactor scram. Repairs were made during the outage and the loop was returned to normal operation. Eleven scrams occurred during the test period caused by 105-KE or 1706-KER.

Declassified 28 Aug 1973. Various methods of producing and using nuclear power for military land vehicles and other military equipment were investigated and evaluated. A nuclear-powered mobile energy depot (MED) would move with advancing armies and produce vehicle fuels from materials readily available in the field. This would make mechanized units independent of external fuel supplies for extended periods, and permit them to move quickly and easily to areas impossible for units that depend on the customary fuel supply lines. Many possible MED systems were evaluated on the basis of energy sources, fuel manufacturing (by both conventional and chemonuclear processes), fuel storage and transportation, and fuel utilization in both present-day internal-combustion engines and power units of the future (i.e., fuel cells). The applications of more than a dozen MED systems to vehicular propulsion were studied. (auth)

A discussion of the hazards and philosophy of plutonium handling is presented. Glove box construction and materials are also discussed along with handling techniques and work being done with plutonium in various parts of this country. (J.R.D.)

This study responds to the requests for data on the subject contained in the D.S. Burrows letter entitled ``Processing Plutonium Scrap`` (symbol FAc:EAS) dated June 30, 1961 and received for reading by Chemical Processing Department Management on July 5, 1961. Cognizance is also taken of the July 5 teletype from G.F. Quinn requesting an appendix updating the content of our document HW-63560 (Pu Reclamation -- January 18, 1960) with regard to safety aspects covered therein. Appendix A of this paper answers this request.

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The operation of a Magnatest Type FM-500 Elastomat instrument, the detection and recognition of the resonant frequencies of a sample, the methods and formulas for the calculation of the elastic moduli from the resonant frequencies, and results obtained from testing several different materials and sample shapes are discussed. The accuracy and reproducibility of the sonic modulus method for graphite was found to be very good. The fundamental flexural resonance was reproducible to within 0.2%, with the reproducibility of the high resonances decreasing to about 0.5%. The data are tabulated. (P.C.H.)

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.

A series of isothermal heat treatments was performed on the highly ordered Al- Fe alloy, 13.6 Alfenol. Resistivity vs. time curves are presented for temperatures of 0 to 700 deg C. (For preceding period see TM-5730.) (C.J.G.)

The experimental work on the diffusion of fission products in graphite matrices at high temperatures is reviewed and the possible mechanisms of mass transport are discussed. Preliminary data are given on diffusion in these systems. It is shown that the rates of diffusion for fission products introduced by a recoil process into the moderatcr lattice can be correlated based on a random wahk solid state diffusion model. An expression is derived for the coefficient of diffusion in terms of the lattice parameters giving the coefficients of diffusion for different atomic species as an exponential function of the atomic radii. The possibility of other controlling mechanisms above 1000 deg C and the effect of carbide formation and other reactions is evaluated. (auth)

This memorandum elaborates on items discussed in a meeting held July 13, 1961 a suggested Spade and Snoopy Program for the Pluto effort. Topics were specific Tory II-C features, basic studies, and miscellaneous items.

A survey of the pertinent literature was made to ascertain the status of data on U/sup 233/ fission-product yields. The various experimental determinations were evaluated, and the most recent mass-spectrometric results were used as a basis for deriving a set of preferred yields. These yields were compared with values reported in two other recent compilations, and for yields >1%, the three setrs agreed with each other to an average precision of <5%. It was concluded that recent measurements have somewhar improved the reliability of U/sup 233/ fission yield data, but some recommendations for additional experimental work were made (auth)

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, Will Wilson, regarding a legal question submitted for clarification: Authority of the Board of Trustees of a school district to require as a prerequisite for entrance of pupils into the first grade that they be inoculated with two Salk vaccine injections for poliomyelitis.