Newly developed multidimensional gamma-ray spectrometric counting techniques permit the direct measurement of twelve fallout radionuclides on air filters. Observed concentrations of Be{sup 7}, Na{sub 22}, Mn{sup 54}, Co{sup 60}, Y{sup 88}, Zr{sub 95}Nb{sup 95}, Ru{sup 106}, Sb{sup 124}, Sb{sup 125}, Cs{sup 134}, Cs{sup 137} and Ce{sup 144} during the past two and a half years help explain the origin and fallout rates of the trace radionuclides in air. 14 refs., 1 tab.

Thulium oxide can be irradiated to meet the desired specific heat generation of 1.5 watts per gram as part of a flux amplification test, which will be conducted the early part of FY-1965. To obtain the heat generation level, is calculated that a 120-day irradiation will be required at a flux of 1.1 {times} 10{sup 14} neutrons/cm{sup 2}-sec. if the proposed target element is modified by reducing the thulium oxide wafer thickness from 0.080 to 0.050 inch. Also, the length of the target element should be reduced to not more than 20 inches to minimize the possibility of sticking in the process tube. This would require four targets rather than a single element as proposed. Prior to undertaking this irradiation, it would be desirable to place a prototype target element in the Hanford Test Reactor to determine the approximate rise factor (change in neutron flux level between the target element and adjacent tubes of fuel elements) in order to more precise data for planning the loading pattern in the production test.

Recent (HCR) Horizonal Control Rod operating problems at the K Reactors, caused primarily by graphite stack distortion, have stimulated several designs of HCR`s capable of operating under adverse conditions. One such design is an aluminum HCR, not completely dissimilar to the present HCR`s, conceived by the Research and Engineering Operation of I.P.D. The successful use of aluminum as a structural material is strongly dependent upon the operating temperature of the aluminum. This study was conducted to determine anticipated operating temperatures of the HCR during reactor operation at the present K Reactor conditions.

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The objective of the production test described in this report is to authorize the irradiation of aluminum-clad fuel elements with U{sup 235}-Al cores for corrosion testing in the 1706-KE Facility; the irradiation of thermocouple elements to measure the temperature of the aluminum cladding, installation of modified rear nozzles on the tubes in which these tests will be conducted., and the use of two regular KE tubes as controls. In order to measure corrosion at higher heat flux and surface temperature than are ordinarily available, corrosion measurement will be made using enriched aluminum-clad fuel elements with ``C`` and ``J`` (U{sup 235} in Al) cores. One fuel element per charge will be provided with thermocouples inserted in the cladding to measure its temperature. These tests will be conducted in the ribless zirconium single-pass tubes in KE Reactor which can be supplied with water from 1706-KE. These fuel elements will have special end supports to avoid disturbances with flaw and heat transfer on the lateral surface. Modified rear nozzles, of the type designed for use with K zirconium tubes, will be installed to permit smooth discharge of elements with these supports.

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This document is a summary of the new Reactor Operations Daily Report, which is to be implemented August 3, 1964. The report explains how the form is to be filled out, and what information is to be entered into the different fields on the form.

The AEC has indicated a need for plutonium with a high concentration of the Pu-240 isotope. Concentrations up to 25 W/o Pu-240 have been requested with a firm commitment given for 25 kilograms of plutonium with at least 18 W/o Pu-240. To meet this production demand, irradiation of depleted uranium, 0.22 W/o U-235, will be undertaken. This test authorizes half of the irradiation in a Hanford K reactor, outlines the general plans, and presents the details of the irradiation. The objective of this test is to authorize irradiation of approximately 12 tons of depleted uranium, 0.22 W/o U-235, in a Hanford K reactor. The depleted uranium will be irradiated to exposures which will yield plutonium with at least 18 W/o Pu-240, an average exposure of approximately 1600 MWD/T.

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Declassified 27 Nov 1973. The cold critical experiments with the Tory II-C reactor were performed in the critical facility of the Lawrence Radiation Laboratory at Livermore. The reactor is described briefly; the experimental equipment and the arrangement for the experiments is described in detail. The core poison was removed without difficulty, and criticality was achieved at 1624 hours July 14, 1965. With the design core configuration the shutdown margin was less than had been intended; criticality was attained at a shim rod bank position of 38.5 inches insertion rather than the expected 35 inches All Hastelloy tie tubes were replaced by Rene'-41. A heated core experiment with DELTA T = 129 plus or minus 7 deg F above room temperature provided a measure of the temperature coefficient which was found to be --3.9 x 10/sup -3/ plus or minus 7% inch of shim rod bank travel/ deg F. Other experiments included flux mapping, using fission foils, fission counters and copper flux wires, transients to determine control element worths, studies of flux spectrum by means of threshold detectors, and measurements of multiplication for various shutdown configurations for purposes of operational safety. Transient measurements, critical rod configurations, and flux distributions were also …

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This document presents the initial definition of a nominal 8 Mwt, SNAP-50 Flight Configuration Nuclear Powerplant Test and is intended to provide guidance to the Architect/Engineer in evaluating and costing various Nuclear Test Facility design concepts.

Research progress on pair production, photoproduction, beta scattering by protons and deuterons, meson ( pi ) production, shielding, polarized photon production, and photonproton scattering is reported. Developments of experimental equipment and facilities are also summarized, together with accelerator improvements and operation. (D.C.W.)

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