Hastelloy-N strip specimens were irradiated in the Oak Ridge Research Reactor at temperatures of 1330 to 1390/sup 0/F, to neutron doses of 1.8 to 2.6 x 10/sup 20/ nvt thermal, l.4 to 2.0 x 10/sup 19/ nvt fast. Twelve irradiated specimens were selected for testing from each of two heats, 0143 (0.010 in. thick) and 5911 (0.015 in.). Six specimens in each heat were as-received, the other six were as-processed. Processing steps included chromizing, a simulated coating firing cycle, diffusion treatment, and straining to simulate tube straightening. In-cell fatigue tests were performed by reverse-bend cycling over mandrels of opposing radii at one cycle per minute, in helium, at 1400/sup 0/F. The twelve specimens tested at strain ranges of 0.61 to 0.75% had an average fatigue life of 97 cycles. Only seven of the specimens tested at strain ranges of 0.31 to 0.37% failed; five remained intact after 25,000 cycles. The average fatigue life for all 0.31 to 0.37% specimens was 15,840 cycles, with no weighting factor used for intact specimens. Experimental results were four times greater than the predicted fatigue life at the higher strain range, fifty times greater at the lower. The Manson method for prediction of Hastelloy-N fatigue …

The infrared imagery data was collected September 13, 1966 from 1010--1013 o`clock, using a mercury-doped germanium detector which was filtered to respond to wave lengths of infrared radiation. The magnetic-tape recorded information was processed with a computer program to obtain quantitative evaluations of river temperature variations and to accurately define surface temperature patterns resulting from the discharge of reactor effluents into the river. The river surface-temperature information collected in the vicinity of the reactor areas was plotted as contours of equal voltage readings which are essentially analogous to isothermal contours. The patterns which developed show clearly: the paths and thermal variations of reactor effluent plumes in the River, points where retention basin subsurface leakage enters the river via the ground water route, and those reaches across from the reactors where the River is recharged by ground water significantly colder than the water released from the Priest Rapids Pool.

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The Nuclear Safety Program at the Richland facilities consists of seven, concurrent subprograms. Which are: Fuel Temperature Transients Under Accident Conditions; Chemical and Metallurgical Reactions and Fission Product Release from Overheated Fuel; Control of Fission Gases; Meteorological Studies; Ground Fixation of Radioactive Material in Liquid Wastes; Particle Formation and Release from Overheated Nuclear Material; and Seismic Studies. The Scope and Objective and Incentives of the overall program are discussed and details provided on each of the seven subprograms.

Declassified 21 Sep 1973. This report covers six programs: (1) studies of substoichiometric urania and urania solid solutions above 1700 deg C and their compatibility with refractory metals; (2) refractory-metal fuel element development for operation in non-oxidizing atmospheres; (3) specific materials properly data for various refractory metals and alloys and refractory-metal--UO/ sub 2/ composites; (4) fission product transport processes in refractory-metal fuel systems at temperatures exceeding 1400 deg C; (5) development of long-life, fueled and unfueled, clad metal hydrides, control elements, and shield materials; and (6) the effect of high fuel burnup on BeOstabilized fuel materials. (DLC)

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The production reactors operated by Douglas United Nuclear, Inc., use treated Columbia River water as the coolant on a once-through basis. Thus, radionuclides formed largely by the neutron activation of river salts are discharged to the river. One method of reducing the quantity of radionuclides in the effluent is to increase the efficiency of parent isotope removal during the coolant treatment process. It was recognized that an alum feed rate of 18 ppM is not necessarily optimum throughout the year. During certain periods it may be well in excess of requirements and overfeeding could be as detrimental to efficient parent isotope removal as underfeeding. Thus, a continuing effort has been underway to find a method for controlling alum feed rate to an optimum value. Flocculent feed rate control based on producing a constant value of the electrokinetic charge (zeta potential) of the floc has been practiced at some water treatment, plants. Although the hypothesis has not had universal acceptance in the water treatment field, laboratory and field data accumulated at Hanford indicated that further evaluation of the approach was warranted. In order to determine the effects of coagulant control based on zeta potential a half-reactor test was initiated at C …

The accompanying table lists the presently selected parameters for the twelve cloud chambers. The chambers are numbered consecutively from 4 through 15 as they are lined up in the bunker. The lowest number is closest to the source. All except the first chamber have some thin metal filters to attenuate the flux and harden the spectrum. Cloud chambers 10, 12, and 14 are shielded by a collimator with about 200 pinholes in it. The flux in these chambers is attenuated by the ratio of the pinhole area to total beam area which is a factor of 50. Various gases and gas pressures are used to obtain suitable track lengths and interaction cross sections. Neon, argon, and krypton are used to obtain photo electrons. Hydrogen is used to obtain Compton electrons.

This document itemizes the irradiations performed by Testing and Irradiation Services for Battelle-Northwest. It lists the materials being irradiated, awaiting disposition and materials shipped during the month of November 1967.

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 month of August 1967.

This report talks about Applications of static converters in power conditioning