Quarterly report describing progress on the EVESR Nuclear Superheat Fuel Development Project.

Report issued by the Oak Ridge National Laboratory discussing progress and work conducted by the Chemistry Division.

Report describing the evaluation of the effects of irradiation on a high pressure water loop that ruptured while testing fuel elements. Includes photographs of the damaged tube as well as chemical analyses.

Report that "describes a system for translating the position of a strip-chart recorder potentiometer shaft into decimal digital form" (p. ii).

Report that "discusses the magnetic vector and scalar potentials, magnetic field components and their derivatives, and flux linkage for single current systems, and the mutual inductance, forces and torques between two such systems, whose axes are coplanar but not necessarily coincident" (p. 1).

Report describing the progress made in the Clinch River Study for the period May to October 1961. This report is based off of multiple reports of water sampling conducted across six stations in order to evaluate the safety and radioactive content of the Clinch River.

As TORY II-C is presently designed, a nuclear excursion would occur if the core were flooded with water. This is true even if all of the existing control rods were fully inserted. Indeed ANGIE calculations indicate that the reactor would be about 30% super-critical in such a case. There are several methods by which the core may be forced sub- critical under these extreme conditions. We will here consider only the method of introducing, directly into the core, a material which strongly absorbs neutrons. It must be possible to remove this excess `poison` prior to, or during the boost phase. Since the computer codes can be trusted to only approximately 3%, we will, for safety, insist on 40% negative reactivity to be introduced by the excess poison.

This paper presents thrust calculations for low altitude trajectories for a Tory II-C type propulsion reactor.

This report summarizes the results obtained in the experimental measurement of the reactor heat extracted by the coolant during two different scrams of the DR Reactor. These tests were conducted with the reactor flow carefully controlled to establish different reactor coolant temperatures following the scram. During normal reactor scrams, which have been used in the past to measure the reactor heat output, a high coolant flow was maintained. Consequently, the coolant outlet temperature dropped very quickly from an operating value of 90 to 95 C down to 20 to 30 C following the scram. Under emergency conditions, however, with only the last ditch emergency flow available, the coolant outlet temperature could remain as high as 80 to 90 C. This condition could prevail because of the small amount of last ditch flow available, and could last for 5 to as long as 70 minutes after the reactor scram.

Report discussing measurements of viscosity made with relative viscometers. These instruments must be calibrated with liquids whose viscosities are known. NBS provides a series of 10 oils for this purpose. Their viscosities range from 0.02 to 450 poises and their temperature coefficients of viscosity range from 2.1 to 9.4 percent per degree C. The less viscous oils are more stable. Correction formulas for errors or conditions are presented.

Report regarding the process development work at the Oak Ridge National Laboratory, including project objectives, design considerations, descriptions of equipment, and estimated costs.

Despite similar atomic arrangement, Brucite (Mg(OH)2) and phlogopite (KMg3(OH)2(Al,Si3)O10) present striking difference in their infrared spectra. A single absorption band is observed in phlogopite whence brucite possesses a total of 15 bands on both sides of the fundamental. A comparison of the hydroxides with micas provides supporting evidence that the complexity of the hydroxide spectra is due to interactions between neighboring hydroxyl groups. Each mineral contains a layer of magnesium ions possessing trigonal symmetry. Both minerals contain hydroxyl ion is located in such a way that it is in contract with three magnesium ions.

Much of the early work in radiation biology was predicted on the assumption that radiation effects could be understood in terms of a single mechanism. This "single mechanism" was studied on appropriate biological test objects that could be developed into biological dosimeters. Attempts were made to assess the properties of "the" biological effects from the relations of "biological dose" (skin dose, bean dose, fly dose, etc.) to physical parameters of irradiation. Notwithstanding the rigidity of this approach, some useful generalizations emerged. During the past 20 years or so, it has become increasingly obvious that ionizing radiations may affect living systems in different ways, and that what is true in one cell, tissue, or species and in one set of circumstances does not necessarily apply to another situation. Accordingly, the search for a single mechanism was replaced by dedicated application to specific detail. In consequence, we now know a great deal about the fine structure of some radiation effects, and there is once again a tendency to formulate generalizations. This paper will attempt to analyze the mechanism of a well-defined syndrome that arises in certain cell systems after a single dose of ionizing radiation. Our attention will be directed mainly to …

When the nucleus of an atom in a crystalline solid undergoes radiative neutron capture there is disruption of the crystal in the vicinity of the event due to energetic processes accompanying the nuclear transformation. This local disruption has been termed a "hot-zone" or "displacement spike". The chemical state of a transformed recoil atom immediately following transformation is unknown. Within a microsecond the "hot zone" has cooled sufficiently to "freeze" the recoil atom into a stable (or metastable) chemical state. A fraction of the metastable recoil atoms can undergo thermal annealing reactions, and the chemical nature of the metastable state can sometimes be inferred from annealing data. It is characteristic of these reactions that the recoil atoms tend to be reincorporated into the parent chemical form.

Information on the metabolism of fission products in man has been obtained largely from studies carried out with parenterally-administered soluble salts of radioisotopes administered in medical treatment or in tracer studies. The recent development of the whole-body gamma spectrometer with its highly sensitive detection system has been of considerable value in extending these studies by providing data on very low levels of isotopes in man over long periods of time.

A description is given of a general-purpose Morte Carlo program for study of the three-dimensional development of high-energy eiectron-photon cascade showers in a homogeneous medium. The results of several study calcuiations are compared with previous analytic work to demonstrate the accuracy of the calculation. Another comparison with an experiment which measured the spatial distribution of the energy deposition in Sn by 185-Mev electron-iritiated showers shows a discrepancy between calculation and experiment. (auth)

A calculation to determine the effectiveness of collimators in a high- energy electron beam is described. Numerical results for a 5-Bev electron beam incident on a 135.42-cm-thick aluminum collimator with an inside radius of 0.85 cm are reported. (auth)

This program was prepared as a pilot program for a larger computer and handles symmetrical reactors with core, side reflector and end reflectors, using 10 radial and 10 axial mesh regions. The output consists of the effective multiplication constant, the two flux distributions, and the fission source distribution. The extrapolated Liebmann process is used for the inner iterations.

The primary objective of this program is to obtain improved data on the changes in nuclear characteristics with burnup of uranium oxide fuel in a boiling water reactor.

The raw materials and fabrication procedures employed in preparing thirty two zirconium alloy compositions for evaluation as described in GEAP-3979 are reported. Considerations involved in the extension of reported laboratory procedures to larger scale production are discussed.

Work has continued on the development of accurate nuclear fuel burnup analysis. Work performed during the fourth quarter is summarized here.

This is the third quarterly report on the work done under Contract AT(04-30-189, Project Agreement No.27, and covers the period August 12 to November 12, 1962.