The present method used for handling multichannelanalyzer data at the ORNL 86-Inch Cyclotron is stated. FORTRAN subroutines for reading the analyzer data into the IBM-7090 computer and for printing out the processed data and punching processed data on cards are presented. (auth)

The SNAP-2 Primary System Test loop fabrication was completed with associated flight prototype components including reactor core and boiler mockups for volume and DELTA P simulation, CRU-IIII NaK pump, compact heater, and expansion compensator. A mobile loading system was designed and fabricated with the capability of cleaning the NaK prior to final loop sealing. Loop descriptions, test objectives, and operating procedures are presented. (auth)

Thermal stresses in the HFIR beryllium reflector were computed for the unlikely case where the reactor is scrammed with a simultaneous loss of coolant flow and for the case following an electrical power outage where the reactor power level and the coolant flow rate are reduced simultaneously. For the case where the reactor is scrammed with a sudden loss of the coolant flow, the resulting maximum tensile thermal stress following the scram is 22,500 psi. In case of an electrical power outage, the maximum tensile thermal stress following a reduction of the fission power level from 100 Mw to 10 Mw with the lowering of the coolant flow rate to 10% of the normal value is 12,800 psi. (auth)

This document details the monthly activities of the Reactor Branch for the period of January 1960 through December 1960.

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The objective of the test was to evaluate the behavior during irradiation of nominally 1.739 inch OD, 1.074 inch ID, Zircaloy-2 jacketed single tube fuel elements with brazed end closures at operating conditions somewhat more severe than those expected for N Reactor fuel element outer tubes. The test elements were fabricated with the Be-Zr alloy brazed end closure planned for use on N Reactor fuel elements. Iron supports were used to minimize process tube scratching during charge-discharge.

This investigation report discusses the exposure of a maintenance craftsman to a radioactive particle found on his face which could have contributed to a dose as high as 4.6 rads. The craftsman had been working at the discharge area. (JL)

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B-Plant is currently being evaluated for use as an integrated fission product plant operating in conjunction with the Purex Plant and a waste calcination system. If the forecasted demands for fission products should increase to rates exceeding present capabilities and if private enterprise continues to remain outside the recovery field, present budget plans are to develop the use of B-Plant in three phases. In Phase 1, the B-Plant canyon would be activated and provisions made for preparing and storing fission product concentrates. In Phase 2, additional equipment would be installed to provide a single-line demonstration system for purifying and packaging fission products. In Phase 3, the plant would be converted to a double-line production system for recovering, segregating and storing, purifying and packaging fission products. The purpose of this document is to present the technical bases for B-Plant project scoping studies, including: Design flowsheets for the preparation and storage of fission product concentrates in the scope design of Phase 1 activities; and conceptual flowsheets for the purification of stored concentrates in the engineering studies of Phase 2 activities.

Selected physical and biological data bearing upon the environmental variations created by nuclear explosions are presented in simplified form. Emphasis is placed upon the ``early`` consequences of exposure to blast, thermal radiation, and ionizing radiation to elucidate the comparative ranges of the major effects as they vary with explosive yield and as they contribute to the total hazard to man. A section containing brief definitions of the terminology employed is followed by a section that utilizes text and tabular material to set forth events that follow nuclear explosions and the varied responses of exposed physical and biological materials. Finally, selected quantitative weapons-effects data in graphic and tabular form are presented over a wide range of explosive yields to show the relative distances from Ground Zero affected by significant levels of blast overpressures, thermal fluxes, and initial and residual penetrating ionizing radiations. However, only the ``early`` rather than the ``late`` effects of the latter are considered.

Antiproton-production and nucleon-interaction cross sections were investigated for antiprotons in the energy range 0.5 to 1.0 Bev. The antiprotons were distinguished from other particles produced at the Bevatron by a system of scintillation- and velocity-selecting Cherenkov counters. The excitation function and momentum distribution were recorded for antiproton production in carbon and compared with statistical model expectations. The antiprotons were directed by a system of bending and focusing magnets to a liquid hydrogen target. An array of plastic scintillation counters, which almost completely surrounded the hydrogen target, was used to determine the p-p total, elastic, inelastic, and charge-exchange cross sections. Near 500 Mev the total d-p cross section was about 120 mb, and it slowly decreased to 100 mb near 1 Bev. The inelastic cross section, which is principally due to the annihilation process, represented nearly 2/3 of the total cross section. The elastic scattering distribution was highly peaked in the forward direction and could be fitted by an optical model. The total and partial cross sections were also determined for the collisions of antiprotons with deuterons. The p-d total and inelastic cross sections were found to be approximately 1.8 times the p-p cross sections. Corrections were made for the shielding …

An investigation was conducted to determine the load at which each of the governor valves open when the primary average temperature is at 500 deg F. Data compilations for the test are presented along with comparisons with past performances. (J.R.D.)

The rapidly increasing volume ot new data in scientific and technical fields demands faster and better ways to communicate the new information to those concerned. A working system. System of Automatic Processing and Indexing of Reports (SAPIR), for doing this is described. SAPIR makes use of the Keyword-in- Context Index principle, by which certain keywords, together with surrounding words that act as modifiers, are selected from the titles of the technical publications. These keywords with their modifiers serve as index entries from each title, therefore there will be as many index entries generated as there are keywords contained in the title. The index entries are sorted alphabetically by the keywords. The first letters of the keywords in each of the index entries form a column in the printed format, which makes scanning for the soughtafter item easier. The SAPIR system is automatic and the list of citations is machine- generated on an IBM 1401 Computer. (auth)

The polarization of the neutrons produced by photodisintegration of deuterium by 2.75-Mev gamma rays was measured and the results compared to theoretical predictions. The photoneutrons were tsken at five gamma-ray-neutron angles between 45 and 135 deg in the laboratory and scattered from magnesium which has a broad resonance at these neutron energies. Tne polarization was determined from the asymmetry in the left-right scattering from magnesium. The neutrons are found to be negatively polarized as predicted. The magnitude of the polarization and the dependence on the gamma-ray-neutron angle were found to be in agreement with the theory within experimental error. (auth)

Results are presented of an investigation to determine the maximum permissible partial pressure of carbon dioxide that could be tolerated in the Maritime Gas Cooled Reactor system without oxidizing and embrittling niobium and its alloys, and to screen the heat-resistant nickel- and iron-base alloys for resistance to oxidation and carburization by hydrogen, carbon dioxide, and carbon monoxide. The effect of hydrogen additions on carburization of heatresisting alloys and on the decomposition of carbon monoxide was also studied along with the cataltic effects of heat-resisting alloys on disproportionation of carbon monoxide. (J.R.D.)

A structural evaluation is presentsd of the Hallam Power Reactor fuel elements. The fuel rcd spacer examined is an interim design, but the final spacer is considered to be adequately represented by the analysis of the interim design. Loading of the spacer is considered at temperatures up to 600 deg F. The maximum stress in the hanger rod is found to be 4700 psi. Creep in the fuel rod cladding from internal pressure is predicted to be 5.2% after 48 months of operation, based on a predicted volumetric growth of 15% caused by irradiation. Data indicate that the actual volumetric growth is only 6%, so that the predicted results are quite conservative. (T. F.H.)

The results of test stand studies of a pneumatic atomizing nozzle to be used in the Demonstrational Waste Calcining Facility at the Idaho Chemical Processing Plant are presented. Atomization and performance characteristics are described. The liquid feed control system for the Demonstrational Waste Calciner is compared with results of bench scale tests, and recommendations are made for improving the system. (auth)

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Residual radioactivity at the Lawrence Radiation Laboratory 184-Inch Cyclotron was measured during November 1960. The study was conducted along three principal lines: (1) general survey of radiation levels in the cyclotron vault, (2) activation of foils placed near the cyclotron, and (3) gamma-ray spectra of the cyclotron gap region, including dee structure. Initial radiation levels were less than 8 r/hr which dropped to abcut 10 mr/hr after 48 hr. The observed activities induced in copper foils were Cu/sup 64/ and Co/sup 58/; in iron foils, Mn/sup 52/, Mn/sup 54/, and Mn/sup 56/; in aluminum foils Na/sup / 2>s/sup 4/ The gamma-ray spectra from the gap region included two intense long-lived peaks, at 510 and 810 kev, caused principally by Co/sup 58/. (auth)