This evaluation of the 296-A-12 stack sampling system is part of a larger study, sponsored by ARCHO and conducted by Battelle-Northwest, of gaseous effluent sampling systems in ARHCO facilities. The objectives of this study are: Evaluate the compliance of the existing effluent particulate sampling system with ARHCO`s Interim Criteria for such systems by using sampling theory and radioactivity counting statistics and make recommendations for corrective action which will lead to a particulate sampling system in compliance with the Interim Criteria. This study is considered preliminary because no experiments have been conducted to verify the sampling system`s performance. The following report includes a brief summary, a detailed description and evaluation of the sampling system, conclusions about satisfactory or deficient areas of the sampling system and recommendations for corrective action. The appendices contain a copy of the Interim Criteria and the applicable ARHCO Emergency Procedure for radioactive gaseous discharges.

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A special array of light pipes was constructed and used with a photodetector to measure the angular distribution of light reflected diffusely from small isolated defects on superfinished nickel spheres. Defects in a size range of concern were detected by the system, and angular distributions of the diffuse light generated by the defects correlated with the defect dimensions. At present, a commercial version of the light sensing array used in this study is not available; however, under development is a more desirable optical system for automated surface certification which will use a photodetector array which is available commercially.

A light reflection technique suitable for development into an automated surface quality certification system was investigated to determine if reflected light intensity distributions could be corre]ated with surface defect depths. Reflected laser light intensity distributions from pit and scratch defects on highly reflective spheres were studied with a commercial multi-element photodetector. It was found that the intensity distributions --Goll'lf be correlated with depths of pits and scratches in a size range of concern on highly reflective' spheres.

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The OF-2 irradiation experiment was designed and built to test candidate High-Temperature Gas-Cooled Reactor (HTGR) fuel and fuel-rod matrix designs. The capsule was designed with two separate specimen cells, allowing for independent temperature control as well as independent fission gas release measurements. The OF-2 capsule is presently operating at the Oak Ridge Research Reactor (ORR). Initial fuel rod linear heat rates are between 16.4 and 23.0 kW/m (5 and 7 kW/ft) and fuel centerline temperatures are approximately 1150 and 1350/sup 0/C. Plans are to operate the capsule for nine ORR cycles to accumulate a maximum damage fluence of 9 x 10/sup 21/ neutrons/cm/sup 2/ (E > 0.18 MeV).

A five-task research program aimed at the development of molten salt thermal energy storage systems commenced in June 1976. The first topical report, covering Task 1, the selection of suitable salt systems for storage at 850 to 1000/sup 0/F, was issued in August 1976. It was concluded that a 35 Wt percent Li/sub 2/CO/sub 3/-65 Wt percent K/sub 2/CO/sub 3/ (LiKCO/sub 3/) mixture was most suitable for the purpose. Interrelationships between various design parameters were examined using the available solutions, and an engineering-scale storage unit was designed. This unit has an annular configuration with a 1-ft OD, 1.5-ft high, 2-in. dia heat transfer well. Preliminary experiments on a pilot size (3-in. OD) unit showed that temperature profiles and progress of the solid-liquid interface agreed with those predicted theoretically. Also, no supercooling was observed during cooldown, and the presence of significant convective mixing was indicated by negligible temperature gradients. Use of a lithium aluminate volume-change suppressor was investigated, but it appears to be nonessential because of the low volume-change in the LiKCO/sub 3/ system. Consideration of the relative heat-transfer resistances under practical conditions suggested that the use of a conductivity promoter will enhance the heat-transfer rates, thereby requiring smaller heat-transfer areas. …

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Presented is an evaluated graphical and tabular compilation of atomic and molecular cross sections of interest to controlled thermonuclear research. The cross sections are tabulated and graphed as a function of energy for collision processes involving heavy particles, electrons, and photons with atoms and ions. Also included are sections on data for particle penetration through macroscopic matter, particle transport properties, particle interactions with surfaces, and pertinent charged particle nuclear cross sections and reaction rates. In most cases estimates have been made of the data accuracy.

Wind-energy measurements conducted by the Lawrence Livermore Laboratory on the island of Oahu, Hawaii, are discussed briefly. Measurement locations in northern Oahu are identified. The measurement site at Kahuku, Oahu, is described. Data obtained at the Kahuku location are summarized as daily and monthly mean velocities for August through November, 1976. Velocity duration curves for each month are also given.

The report discusses the current status of liquid-metal fast breeder reactor (LMFBR) development and one of the principal safety issues, a hypothetical core-disruptive accident (HCDA). Bibliographic information on worldwide LMFBRs relative to the development of the breeder reactor as a safe source of nuclear power is presented for the period 1972 through 1974. The bibliography consists of approximately 1380 abstracts covering research and development and operating experiences leading up to the present design practices that are necessary for the licensing of breeder reactors. Key-word, author, and permuted-title indexes are included.

This report describes a computer code written in LLL modified Fortran IV that can be used on a CDC 7600 for calculating personnel doses due to exposures to tritium. The critical organ is body water. The code is capable of handling various exposure situations, and is also capable of detecting a large variety of data input errors that would lead to errors in the dose assessment.

Recycle fuel for the High-Temperature Gas-Cooled Reactor (HTGR) contains a weak-acid-resin (WAR) kernel, which consists of a mixture of UC/sub 2/, UO/sub 2/, and free carbon. At 1900/sup 0/C, BISO-coated WAR UC/sub 2/ or UC/sub 2/-UO/sub 2/ kernels lose a significant portion of their uranium in several hundred hours. The UC/sub 2/ decomposes and uranium diffuses through the pyrolytic coating. The rate of escape of the uranium is dependent on the temperature and the surface area of the UC/sub 2/, but not on a temperature gradient. The apparent activation energy for uranium loss, ..delta..H, is approximately 90 kcal/mole. Calculations indicate that uranium loss from the kernel would be insignificant under conditions to be expected in an HTGR.

Solution channels in quartz, microcline, and plagioclase of a granite were produced by exposure of the rock to an artificial hydrothermal system. Electron microprobe analyses, beam-scanning photographs, and element profiles show that the mineral grains are homogeneous and unaltered within a few micrometers of the channels. The channels, which are 3 to 7 ..mu.. in diameter, appear to have formed by removal of material in solution. In the sample material, no new minerals produced by alteration or deposition were detected by microprobe analysis. The apparent absence of such alteration products (e.g., clays) may be due to (1) sample preparation which removed fine-grained alteration products during polishing; or (2) concentrations of such minerals in such small amounts that they are below the limits of detectability with the microprobe. The granite is seen to be preferentially attacked by the hydrothermal solution along grain boundaries and cracks. Similar solution effects are observed in amphibolites exposed to the artificial hydrothermal system. Plagioclase crystals in the amphibolite are partially dissolved so that delicate porous boxwork structures remain.

The neutron spectrum in the FTR Engineering Mockup Critical has been measured at six locations using proton-recoil techniques. At three of these locations, multiple foil irradiations were also conducted. Two-dimensional diffusion theory calculations using 42 energy group ENDF/B-III cross section data were made and the spectra from these calculations were compared to the proton-recoil data and spectra inferred from analyses of the irradiated foils. In general, the diffusion theory results agree quite well with the proton-recoil results. Good agreement was also obtained using the multiple foil technique for in-core locations. However, low fluence levels led to unreliable multiple foil results for the shield location.

Magnetoresistivity measurements are performed in fields up to 40 kOe on some concentrated amorphous La--Gd--Au alloys exhibiting characteristics of a spin-glass. The negative magnetoresistivity at low temperature is found to be roughly proportional to the square of the magnetization. The resistivity minima in these alloys are attributed to a mechanism of electron scattering from magnetic clouds coupled by the RKKY interactions, in qualitative agreement with analysis of remanent magnetization data. 4 figures, 1 table.

Presented is an evaluated graphical and tabular compilation of atomic and molecular cross sections of interest to controlled thermonuclear research. The cross sections are tabulated and graphed as a function of energy for collision processes involving heavy particles, electrons, and photons with atoms and ions. Also included are sections on data for particle penetration through macroscopic matter, particle transport properties, particle interactions with surfaces, and pertinent charged particle nuclear cross sections and reaction rates. In most cases estimates have been made of the data accuracy.

The tritium effluent control project to reduce emissions at Mound Laboratory and its application to liquid wastes are described. Research progress reported includes increasing the power of the Nd:YAG laser for detritiating voluminous wastes by molecular photoexcitation, and analysis of gas produced from tritiated water and octane. (DLC)

The Data Model, i.e., the information content of the data base as it is viewed by the users, of the BNL Archive and Dissemination System is presented. The syntax of the data model is stated in BNF form, and the semantic meaning is discussed. Examples of the use of the data model are given. 3 figs.

Since 1971 discussions have been held at Brookhaven National Laboratory on the desirability of construction of a storage ring which would be used exclusively for production of intense beams of photons with wavelengths in the ultraviolet and X-ray ranges. A proposal is given which discusses in detail the machine, its characteristics, and its expected uses. The proposal includes: (1) characteristics of synchrotron radiation; (2) scientific justification for a synchrotron radiation facility; (3) facility design; (4) wiggler magnets; (5) experimental facilities; (6) buildings and utilities; (7) construction schedules, costs, and manpower; and (8) environmental assessment.

Lithium flows on the inside surface of a porous spherical shell are analyzed to determine their stability characteristics against small perturbations in (1) the film thickness, (2) the colatitude component of the lithium velocity, and (3) the rate of mass supply of lithium through the porous wall. A linearized stability analysis is developed, and it is concluded that lithium film flows are stable against these types of perturbations.

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The principal aim of the National Waste Terminal Storage (NWTS) program is to develop repositories in several different rock formations in various parts of the country. Rocks such as salt, shale, limestone, and granite may qualify as host media for the disposition of radioactive wastes in the proper environments. In general, the only requirement for any rock formation or storage area is that it be able to contain any emplaced wastes for so long as it takes for the radioactive materials to decay to innocuous levels. This requirement, though, is a formidable one because some of the wastes will remain active for periods of hundreds of thousands of years and because the physical and chemical properties of rocks that govern circulating ground water and, hence, the containment may be difficult to determine and define. Rock salt has long been regarded as the most favored geologic medium for the containment of radioactive wastes in the United States. This stems largely from the plastic behavior of salt, which promotes self-healing and otherwise makes it impermeable to circulating ground water. Other important advantages of salt include its wide distribution, ease of mining, and favorable heat dissipation characteristics. In addition to the salt domes …

A day-to-day account of the work done at the University of Chicago Metallurgical Laboratory from April 1942 to April 1943 is given. The work concerned the development of chemical procedures for the extraction of plutonium, for the purification of plutonium, and, in the later phases, for research on the isotopes of other heavy elements including other transuranium elements. (LK)