An rf system is described for the 500-MHz cylindrical resonator that is coupled to the Astron beam to modulate its energy by +- 1.5 percent.

Quantitative test data are presented for two etched and plated uranium alloys, U-0.75 Ti and mulberry (U-7.5 Nb, 2.5 Zr). Conical head tensile tests showed that the bond between nickel plating and U--Ti was stronger than that between nickel plating and mulberry. Ring shear tests showed that electroplated nickel coatings are more adherent than other coatings applied to U--Ti. Utilizing a newly developed etchant for mulberry, large cylinders of this material were joined to aluminum and then tensile tested. Results showed that the strength of the joint was directly influenced by the taper angle on the mulberry.

A theoretical model was used to study the effects of structured electrodes on converter I-V characteristics and results are given. An auxiliary-ion-source triode operated as a plasmatron was used for studying the enhancement distribution and magnetic effects, and results are reported. Design features of the high current--zero power (ZEPO) converter tests are given. (WHK)

Volume I of the five-volume report contains executive and technical summaries of the entire report, background information of the LWR fuel cycle alternatives, descriptions of waste types, and projections of waste quantities. Overview characterizations of alternative LWR fuel cycle modes are also included. (JGB)

Volume II of the five-volume report is devoted to the description of alternatives for waste treatment. The discussion is presented under the following section titles: fuel reprocessing modifications; high-level liquid waste solidification; treatment and immobilization of chop-leach fuel bundle residues; treatment of noncombustible solid wastes; treatment of combustible wastes; treatment of non-high-level liquid wastes; recovery of transuranics from non-high-level wastes; immobilization of miscellaneous non-high-level wastes; volatile radioisotope recovery and off-gas treatment; immobilization of volatile radioisotopes; retired facilities (decontamination and decommissioning); and, modification and use of selected fuel reprocessing wastes. (JGB)

Volume III of the five-volume report contains information on alternatives for interim storage and transportation. Section titles are: interim storage of spent fuel elements; interim storage of chop-leach fuel bundle residues; tank storage of high-level liquid waste; interim storage of solid non-high-level wastes; interim storage of solidified high-level waste; and, transportation alternatives. (JGB)

Volume IV of the five-volume report contains information on alternatives for final storage and disposal of radioactive wastes. Section titles include: basic concepts for geologic isolation; geologic storage alternatives; geologic disposal alternatives; extraterrestrial disposal; and, transmutation. (JGB)

Volume V of the five-volume report consists of appendices, which provide supplementary information, with emphasis on characteristics of geologic formations that might be used for final storage or disposal. Appendix titles are: selected glossary; conversion factors; geologic isolation, including, (a) site selection factors for repositories of wastes in geologic media, (b) rock types--geologic occurrence, (c) glossary of geohydrologic terms, and (d) 217 references; the ocean floor; and, government regulations pertaining to the management of radioactive materials. (JGB)

Begun in 1970, the Amchitka Radiobiological Program is a continuing program to collect biological and environmental samples for radiometric analyses. This report is an account of the program for Calendar Year 1975. Results of analyses for samples collected in August 1975 have been added to the tables that summarize the results of analyses of samples collected from 1970 to 1975 and include analyses for gamma-emitting radionuclides in air filters, freshwater, birds, lichens, marine algae, marine invertebrates, fish, aufwuchs, and freshwater moss and plants; strontium-90 (/sup 90/Sr) in rats, birds, and soil; /sup 239/ /sup 240/Pu in sand, soil, marine algae and fish; and tritium (/sup 3/H) in seawater, freshwater, and biological organisms. Monitoring of background radiation with survey instruments was added to the Laboratory's program in 1974 and the results of the 1974 and 1975 surveys are included in this report. It is concluded from the results of analyses of samples collected between September 1969 and August 1975 as reported in this and the five previous progress reports, that there were no radionuclides of Milrow or Cannikin origin in the water, plants, or animals of Amchitka Island.

The production of carbon monoxide observed within Multihundred Watt heat sources placed under storage conditions was analyzed. Results of compositional and isotopic analyses of gas taps performed on eight heat sources are summarized and interpreted. Several proposed CO generation mechanisms are examined theoretically and assessed by applying thermodynamic principles. Outgassing of the heat source graphite followed by oxygen isotopic exchange through the vent assemblies appears to explain the CO production at storage temperatures. Reduction of the plutonia fuel sphere by the CO is examined as a function of temperature and stoichiometry. Experiments that could be performed to investigate possible CO generation mechanisms are discussed.

Of the available high strength ceramics, silicon nitride offers the most promise followed by silicon carbide and aluminum oxide, and stress analyses show severe limitations on allowable velocities for impact with granite following reentry for these ceramics. Impact velocities in the 100 to 200 fps regime can be achieved only by the addition of an additional layer to distribute the high contact stress. Besides impact limitations, application of ceramic materials in heat sources would present problems both in terms of weight and fabrication. The required thickness of a ceramic impact member would be comparable to that for a carbon-carbon composite material, but the least dense of the high strength ceramics are 2 to 3 times more dense than the carbon-carbon composites. Fabrication of a ceramic heat source would require a high strength bond between the fuel and the impact member if reasonable impact velocities are to be achieved. Formation of such a bond in ceramic materials is a difficult task under normal circumstances, and would be more difficult under the restrictions imposed on the processing and handling of the /sup 238/PuO/sub 2/ fuel. 16 fig.

Evidence is presented which suggests that a low-temperature, martensite-like behavior may be quite general in actinide metals and their alloys and compounds. There may be no metastable martensitic embryos in an ..cap alpha..-phase structure of high-purity U, Np, and Pu formed by a diffusion-controlled ..beta.. ..-->.. ..cap alpha.. transformation, and thus no evidence for low-temperature phases. The effect of impurity content on observed low-temperature physical properties of these actinides is noted. It is proposed that impurities may be playing several roles. They may permit an electron redistribution in dilute alloys dependent upon the length of holding time. Experimentally determined values for the electronic contribution to heat capacity and the density of states of U, Np, and Pu should thus vary over a considerable range, as has been observed. Variations in interstitial ordering of impurity atoms with processing may yield stacking variants of each basic close-packed actinide metal structure and thus determine the number and structure of low-temperature phase. 46 references.

Relaxation techniques which have been used in connection with the factorization iterative methods are reviewed. Known properties are summarized, and new ones are obtained. A precise meaning is given to the notion of iterative procedures of order q, and the two-parameters overrelaxation technique of Woznicki is shown to be a factorization iterative method of the second order; some consequences of this fact are developed. Other results include the refinement of known properties of the extrapolation principle and estimations of the powers of the Oliphant relaxation technique for consistently ordered matrices and of the Chebyshev technique for Stieltjes. 4 figures.

An equilibrium analysis has been made of the fission-product cesium in the primary coolant loop of the high-temperature gas-cooled reactor (HTGR). The species distributions that result at equilibrium have been calculated for various conditions of reactor operation. The cesium species considered were the monomer, dimer, oxides, hydroxides, and the hydride. The effect of cesium sorption isotherms on graphite also was included in the analysis. During normal reactor operations, the abundant species of cesium were calculated to be elemental cesium, Cs, and the monomeric hydroxide, CsOH. Under most conditions of steam ingress, the abundant species was calculated to be CsOH. Cesium adsorbed onto graphite was stable under all steam-ingress conditions considered. Thermal transients above 1500/sup 0/K were required for equilibrium transport of cesium from the core to the coolant. The analysis was carried out using the complex equilibrium code QUIL, designed and written with special emphasis on features that make it applicable to the fission-product problem.

Results are presented of a study aimed at determining the feasibility of using chemical getter beds to scavenge tritium from inert gases. Two types of getter bed, fixed and fluidized, were considered, using cerium as the getter material. Mathematical-modeling results and capital-cost estimates indicate that not only is the gettering approach technically feasible, it could lead to considerable cost savings over catalytic oxidation, the tritium-removal method traditionally used.

A description and interpretation of the atomic spectrum of neptunium are given. Wavelengths were measured for 6096 spectrum lines in the range 3793 to 38,812 cm/sup -1/ (26,353 to 2575 A), of which 2526 were classified as transitions between 329 odd levels and 130 even levels of neutral neptunium (Np I). The data are presented in five tables.

This standard establishes the requirements for austenitic stainless steel seamless hexagonal duct tubes for fuel, control rod, and other core component assemblies.

The CHSH inequality is demonstrated from locality alone without using either determinism or the concept of hidden variables. Then a comment is made about the violation of this inequality by quantum theory. (JFP)

An approximate solution is developed for natural convection in porous media resulting from localized heat sources. The method is applicable for moderate levels of convection. Results of the method compare well with those of other calculational methods and with experimental data. The solution for a spherical source can be used as an indirect method for the determination of permeability in some cases.

General requirements for the Brayton Isotope Power System (BIPS)/Ground Demonstration System (GDS) assembly and test facility are defined. The facility will include provisions for a complete test laboratory for GDS checkout, performance, and endurance testing, and a contamination-controlled area for assembly, fabrication, storage, and storage preparation of GDS components. Specifications, schedules, and drawings are included.

The government, AIRPHX, AIRLA, and contractor BIPS program coordination efforts are discussed. These coordination efforts are essential for defining program objectives, and achieving these objectives in an efficient manner. The IPP outlines a long range effort intended to: (a) develop end product confidence; (b) identify government and contractor activities pertinent and contributory to BIPS development; (c) recommend government and contractor activities required to ensure BIPS program success; (d) establish activity priorities based on program cost and schedule impacts, and achievement of technical objectives; (e) coordinate the efforts of contributing agencies; (f) provide general information and, to a limited extent, BIPS program-related development activity status to interested individuals and agencies; and (g) provide contractor team program planning guidance.

The BSR operated at an average power level of 1,878 kw for 38.00 percent of the reporting period. Water-quality control in both the reactor primary and secondary cooling systems was satisfactory. There were two unscheduled shutdowns during the quarter. The PCA was not used during the report period and remains in a secured condition.

The BSR operated at an average power level of 1,996 kw for 31.93 percent of the time during the report period. Water-quality control in both the reactor primary and secondary cooling systems was satisfactory. An unscheduled shutdown occurred on October 31, 1975, because of water loss from the pool at a rate of 1.6 gpm, apparently due to several small leaks. The reactor fuel was transferred to the OGR Canal Storage and the pool water level lowered to the pool floor. Defective areas in the concrete pool walls and floor are being chipped, grouted and sealed in preparation for applying fiberglass and repainting. Pool repairs accounted for 98 percent of the downtime reported. The PCA was not used during this report period and remains in a secured condition.

Several corrosion- and heat-resistant alloys are being considered for long term applications in coal gasification plants at temperatures up to 1.255/sup 0/K in high pressure environments of mixed hydrogen, water, hydrocarbons, and sulfides. A method for in situ testing has been developed for short time mechanical tests of candidate alloys in high pressure, high temperature, gaseous environments, referred to as coal gasification atmosphere (CGA). The method involves bursting thin-walled tubes, using various gases to produce the burst hoop stress. The short time 1.255/sup 0/K burst and creep rupture strength and ductility properties of alloys 800 and 800H in a mixed gas environment, H/sub 2/, CO, CO/sub 2/, CH/sub 4/, SO/sub 2/ (CGA), are not reduced from properties obtained in air. However, the stress- and pressure-accelerated corrosion is more severe in CGA. It is expected that CGA will reduce long term strength and ductility in alloy 800 as a result of the accelerated corrosion. The short time 1.255/sup 0/K strengths of alloy 310 in CGA and pure hydrogen environments are reduced from the values obtained in air by less than 10 percent. The ductilities (total circumferential elongation) are good--approximately 20 percent for all test conditions. The CGA stress- and pressure-accelerated corrosion …