The test detailed in this report authorizes the installation of sampling tubes in the vacant-positions in one of the two front-to-rear graphite stringers to be installed in KW Reactor in January 1963. These lines will permit withdrawal of a gas sample from the active zone at a point where the graphite temperature is being measured. Analysis of this gas sample on the gas chromatograph and on a new catalytic oxygen-hydrogen instrument is expected to yield valuable information on graphite burnout versus temperature and gas quality.

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The objective of this production test was to evaluate the irradiation behavior of N. Reactor fuel elements at conditions equivalent to or more severe than those expected in N Reactor. The thermocouple train consisted of eleven 23-inch NAE1 elements (replicas of an N Reactor fuel element) plus five 16-inch tubular perfs. The elements were enriched to 0.947 per cent. They were coextruded Zircaloy-2 jacketed self-supported uranium tubes concentrically nested one within the other to provide an element with four heat transfer surfaces and three coolant channels. For specific dimensions, refer to Production Test IP-477-A.

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The tests performed on a full-scale prototype of the closure designed for the Pathfinder reactor vessel are described. This head was bolted to another head designed to simulate the reactor vessel. The design pressure of the facility is 700 psig at 500 deg F. Strain gages and brittle coatings were used to determine the stresses in the closure. Dial indicator gages were used to measure flange rotation after the head was secured and while it was subjected to hydrostatic pressure. Tests were performed at reactor operating temperature and pressure to evaluate the closure and gasketing. The vessel was thermal cycled, and temperature gradients in the head measured to establish allowable heating and cooling rates. Hydraulically operated bolt tensioners were used to seal and open the closure. Special tools and procedures were developed for underwater operation. (auth)

Organization of the ORNL Operations division for administration of the Oak Ridge Research Reactor, the Low Intensity Testing Reactor, and the Oak Ridge Graphite Reactor is described. (J.R.D.)

Experimental studies of the relative atomic mu --meson capture probabilities in the constituents of chemical compounds are described. Fermi and Teller had predicted that the atomic-capture probability is proportional to the nuclear charge of the atomic species weighted by its atomic concentration. This is sometimes referred to as the Fermi-Teller Z law.'' Previous experiments indicated no clear systematics to this capture process, and there are conflicts between the results of several measurements made with the same or similar compounds. In these experiments the capturing atom was identified by detection of either mesic x rays or decay electrons from mu /sup -/ mesons bound in the mesic K shell in the atomic species, In these experiments oxides and sulfides of some medium- and high-Z elements as well as two metallic solutions were used, and a nuclear capture product (neutron) rather than the decay electrons was detected. Results show that among the substances examIned, namely CuO, Sb/sub 2/O/sub 3, PbO, CuS, Sb/sub 2/S/sub 3/, PbS AgLi, and CuAu, the Z law'' behavior is not indicated either in insulators or in metals, although in all cases there is a preference for capturing in the atom of higher Z. If the atomic-capture probability is …

This report, for July 1962 from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; employee relations; and safety and security.

The Oak Ridge National Laboratory has three generalpurpose research reactors which accommodate testing loops, target irradiations, and beam-type experiments. Since the experiments must share common or similar facilities and utilities, be designed and fabricated by the same groups, and meet the safe safety criteria, certain standards for these have been developed. These standards deal only with those properties from which safety and economy of time and money can be maximized and do not relate to the intent of the experiment or quality of the data obtained. The necessity for, and the limitations of, the standards are discussed; and a compilation of general standards is included. (auth)

This report, for June 1962 from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; employee relations; and safety and security.

A detailed analysis of the PM-2A steam generator tube sheet revealed that is is safe from strain cycling damage. The pressure stresses, however, indicated that permanent deformation would take place in the tube sheet at hydrostatic test pressure of 1.5 times design pressure. (auth)

Compressors were required to circulate helium coolant in an in-pile loop at moderately high heads (6000--8000 ft), at low volumetric flows (30--40 acfm), at 600 deg F and 385 psig. A regenerative type of gas compressor, using greaselubricated ball bearings enclosed in a special water-cooled casing, was designed and tested. The design objectives were achieved, and a number of these compressors have been built and are in operation. (auth)

A new outlet elbow fitting has been designed for use on C reactor to replace those elbows which fail because of stripped threads where the elbow connects to the rear nozzle barrel. There are two models of this threadless elbow, one providing for a water thermocouple only, and one providing for a thermocouple and an RTD. Flow tests have been conducted to determine the pressure drop across these outlets and the pressure drop has been compared to the pressure drop across the previously used outlet elbow and pigtail assembly. Results of these tests and comparisons are shown.

A spectrographic method was developed for the complete cation analysis of high-purity water by spark excitation of the evaporated sample on pairs of silver electrodes. The procedure is fast and precise, with a minimum of sample handling and adequate sensitivity for determining verv small amounts of trace impurities. (auth)

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A two-foot-square fluidized bed calciner was designed and operated to convert aqueous, highly radioactive wastes into granular solids. The calciner exceeded its designed feed capacity of calcining, at a bed temperature of 400/sup 0/C, 100 liters per hour of aluminum nitrate solution simulating wastes from the reprocessing of spent aluminum-uranium alloy reactor fuel. Heat was supplied to the calciner by circulating NaK with an electromagnetic pump, at temperatures up to 1400/sup 0/F, through a tubular heat exchanger placed directly in the fluidized bed of solids. The results of ten runs are presented and discussed. Equipment development progressed to the point where a continuous, trouble-free, operating period of 43 days was attained. Several properties of the alumina product were routinely measured, and some of the effects of the calciner operating variables on these properties were determined. The production of both amorphous and alpha crystalline material was found to be possible; the crystalline nature of the product had a profound effect on product properties and off-gas loading.

This is one of twenty-one volumes summarizing the Aircraft Nuclear Propulsion Program of the General Electric Company. This portion describes work on Metallic Fuel Element Materials.

This memorandum discusses study areas and items that will require attention for the naval studies of the utilization of nuclear propulsion in a submarine-based missile system.

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Pilot plant studies were conducted to develop a continuous process for recovering uranium from nichrome fuels (HTRE). The process consisted of dissolution of fuel in mixed HCl--HNO/sub 3/ solution, removal of the chloride ion by stripping with HNO/sub 3/ in a packed column, and then recovery of the uranium by TBP solvent extraction. Recovery of uranium from nichrome fuels at satisfactory rates and efficiencies can be obtained by this process. Reactor fuels containing large amounts of silica may present a solids problem during chloride removal. Titanium is a suitable material of construction for the dissolver, stripping column, and their associated equipment (feed, off-gas, and product vessels). Stainless steel equipment is suitable for the solvent extraction system. (auth)

A superposition model is developed to predict the critical heat flux in forced convection flow. The model is applied to available experimental results in boiling water flows and good agreement is obtained between the model and test data over the multitude of geometries, flow rates, pressures, and fluid enthalpies tested to date. (auth)

Criteria and guide lines are presented for the design, construction, and operation of safe, economical, and efficient glove boxes and associated facilities based upon present conditions and anticipated changes. Comprehensive discussion of glove box materials and components, safety and fire prevention methods, health physics problems, operational considerations, and brief descriptions of AEC installations are included. (39 references) (C.H.)

The SNAPSHOT Safety Program, as described in this document, is therefore formulated to align safety studies performed by separate agencies and their contractors. At the present stage in program development, the plan is principally concerned with the initial SNAPSHOT flight (SNAP 10A). SNAPSHOT represents a special flight mode for the initial reactors operated in space. The flights are designed to permit early space reactor tests prior to resolving all the safety proglems that may be associated with more advanced programs. Of primary significance is that reactor operation will not be initiated until an orbit of satisfactory lifetime has been obtrained, thus ensuring the long-term decay of the fission products producted prior to re-entry.