Work during the period was devoted primarily to a range of analytical/numerical investigations, including evaluation of means to improve external blanket designs, beneficial attributes of the use of internal blankets, improved methods for the calculation of heterogeneous self-shielding and parametric studies of calculated spectral indices. Experimental work included measurements of the ratio of U-238 captures to U-235 fissions in a standard blanket mockup, and completion of development work on the radiophotoluminescent readout of LiF thermoluminescent detectors. The most significant findings were that there is very little prospect for substantial improvement in the breeding performance of external blankets, but internal blankets continue to show promise, particularly if they are used in such a way as to increase the volume fraction of fuel inside the core envelope. An improved equivalence theorem was developed which may allow use of fast reactor methods to calculate heterogeneously self-shielded cross sections in both fast and thermal reactors.

During operation of the prototype FFTF sodium pump, it is necessary to know the position of the pump shaft relative to the sodium-lubricated hydrostatic bearing journals. Performance of the Kaman proximity measurement system was known to be affected by the type of media between the gap to be measured. Since Kaman Sciences Corp. did not have liquid sodium testing capabilities, LMEC was requested to evaluate a spare prototype system. Determination of the sodium performance characteristics of the Kaman proximity systems was a necessary requisite for use of four prototype systems in the FFTF prototype pump test program.

The objective of this program is to evolve and define an accessory drive system that will minimize system power consumption of driven accessories on an internal combustion engine in a passenger automobile. The initial program phases established concept feasibility, determined potential fuel savings, and selected a drive system design for concept mechanization. The present Phase IV carries the program through prototype fabrication and bench, engine, and vehicle tests. The final program objective is a detail drive system design and a demonstrated overall vehicle fuel savings potential. The major technical accomplishments during this reporting period were: hydromechanical and mechanical variable-ratio belt drive fabrications completed; compact vehicle fuel economy analysis completed; initial engine check runs for both drive systems were completed; mechanical drive system development and performance mapping was initiated; hydromechanical drive system development tests and modifications were initiated; the hydromechanical drive system installation into the test vehicle was completed; the engine/dynamometer test rig, including accessory load simulators, was completed; and the basic test vehicle instrumentation was completed. (LCL)

The S/sup 3/ Financial Projection Model is an effort undertaken to construct a pipeline economic model in order to satisfy the requirements of the US ERDA program: Energy Study of Pipeline Transportation System. A brief outline of this process is described in Appendix A, Background on the S/sup 3/ Development of a Pipeline Economic Model. A general overview of the model is presented first to indicate the rationale underlying the model and to show the linkages between the various submodels. An understanding of the basic accounting definitions and self-evident relationships between line items in the general financial accounting reports is a prerequisite for the effective application of the model. Particular attention has been paid in this system description to defining the methods of calculations utilized by the model and to describing the optional capital investment planning techniques that may be exercised with the model. The mathematical relationships underlying various planning techniques are defined and the methods for applying these techniques are discussed with illustrations and sample input data specifications. Decision tables are used to show complex decision rules applied within the model to determine the logical flow of a particular computational routine. The complete set of source data and model …

A study of commercially available and prototype aerodynamic drag reduction devices which can be retrofitted onto this nation's trucks to achieve significant fuel savings by 1980 was conducted. The results of the study are presented in seven sections. An overview of the basic study results is given in the Summary Section, and a brief introduction to the general nature of the truck drag problem and the study scope is contained in Section 1. Section 2 provides a more detailed discussion of the aerodynamic drag problem and the characteristics of specific retrofit aerodynamic drag reduction devices which are in the production or prototype status. The results of a survey of fleet owners utilizing aerodynamic drag reduction devices and their experience with regard to fuel savings and operational factors are given in Section 3. Section 4 contains the results of economic analyses made to determine the cost-benefit effects of drag reduction devices. An analysis of the US truck population to which such drag reduction devices may be applicable and the fuel savings potential attendant to their use is given in Section 5. The significant elements of a program structured to encourage the utilization of aerodynamic drag reduction devices on trucks are defined …

The three-volume report describes a dual-mode nuclear space power and propulsion system concept that employs an advanced solid-core nuclear fission reactor coupled via heat pipes to one of several electric power conversion systems. Such a concept could be particularly useful for missions which require both relatively high acceleration (e.g., for planetocentric maneuvers) and high performance at low acceleration (e.g., on heliocentric trajectories or for trajectory shaping). The first volume develops the mathematical model of the system.

The three-volume report describes a dual-mode nuclear space power and propulsion system concept that employs an advanced solid-core nuclear fission reactor coupled via heat pipes to one of several electric power conversion systems. The second volume describes the computer code and users' guide for the preliminary analysis of the system.

The axisymmetric buoyancy-induced groundwater flow adjacent to horizontal impermeable surfaces with wall temperature being a power function of radius is discussed in this paper. With the boundary layer simplifications, the governing non-linear partial differential equations can be transformed into a coupled pair of non-linear ordinary differential equations with two-point boundary conditions that can be integrated numerically by established techniques. Simple algebraic expressions for boundary layer thickness and heat transfer rate are obtained. Applications to free convective flow in a liquid-dominated geothermal system at high Rayleigh number are discussed.

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The study assesses the value of seismic trip (scram) systems on commercial nuclear power plants. Five topics were specifically addressed: (1) the likelihood that existing instrumentation would trip the plant; (2) the consequences of spurious trips; (3) the consequences of tripping during an earthquake; (4) the advantages of a controlled shutdown; and (5) the desirability of continuing operation. A comparative risk assessment was made based on evaluation of fault trees constructed for plants with and without seismic trip systems. It was found that seismic trip systems would have a small and undetermined effect on risk due to nuclear reactor accidents and may indeed increase the risk to society from an earthquake.

Research work in smart, unmanned limbed vehicles for naval warfare applications performed during the latter part of FY76 and FY76T by the Special Studies Group of the LLL Physics Department for the Office of Naval Research is reported. Smart water-traversing limbed remotely navigated vehicles are interesting because: they are the only viable small vehicle usable in high sea states; they are small and work on the ocean surface, they are much harder to detect than any other conventional craft; they have no human pilot, are capable of high-g evasion, and will continue to operate after direct hits that would have crippled a human crew; they have the prospect of providing surface platforms possessing unprecedented speed and maneuverability; unlike manned information-gathering craft, they impose almost no penalty for missions in excess of 10 hours (no need to rotate shifts of crewmen, no food/lavatory requirements, etc.) and, in their ''loitering mode'', waterbugs could perhaps perform their missions for days to weeks; they are cheap enough to use for one-way missions; they are mass-producible; they are inherently reliable--almost impossible to sink and, in the event of in-use failure, the vehicle will not be destroyed; they maximally exploit continuing technological asymmetries between the U.S. …

The overall objective of the Systems for Nuclear Auxiliary Power (SNAP) Program is to continue system and component engineering activities relating to the zirconium hydride (ZrH) reactor. The specific objectives for FY 1976/TQ were to: (1) study standardized ZrH reactor space power systems and components, (2) perform preconceptual analysis and design of ZrH reactor--organic Rankine power systems for subsea applications, (3) conduct fuel and hydrogen barrier investigations, (4) perform system studies in support of the Department of Defense and their contractors as directed by ERDA, (5) test components, and (6) provide for material disposal and facility surveillance. In the study, representative systems which utilize Brayton, Rankine, and Stirling cycle power conversion units as well as thermoelectric modules, are analyzed at power levels of 10, 25, 50, and 75 kWe. Waste heat rejection is accomplished by concentric, cylindrical space radiators which can be nested during launch for space shuttle integration. Subsequent studies, which supported this effort, were completed and provided useful information on system reliability and survivability.

The safety engineering effort to be undertaken in achieving an acceptable level of safety in the Brayton Isotope Power System (BIPS) development program is discussed. The safety organizational relationships, the methods to be used, the tasks to be completed, and the documentation to be published are described. The plan will be updated periodically as the need arises.

A method for storing heat energy by utilizing reversible chemical reactions of inorganic oxides with water is under investigation at Atomics International. The system design requires a knowledge of rates of the dehydration and hydration reactions, and, in order that these rates be significant for practical applications, it must be shown that these rates are maintained as the material is cycled repeatedly through the anhydrous and hydrated condition. For solar heat storage operating on a daily cycle, for example, a 3-yr life requires somewhat more than 1000 cycles. Besides the effect of cycling on reaction kinetics, the extent of corrosion by the inorganic oxide/hydroxide on its containment vessel during cycling is an important parameter. Also, since one form of the active material that appears to have some advantages is that of granules held together by an inorganic cement, it is important in this case to know if the granules are broken down by cycling.

The experimental approach to attaining the goals of this research program is briefly outlined, and the progress made in the last year is reviewed in sections entitled: (a) Primary steps in the reactions of recoiling silicon and germanium atoms and the identification of reactive intermediates; (b) Thermally induced silylene reactions; (c) The role of ionic reactions in the chemistry of recoiling silicon atoms and other ion-molecule reaction studies.

A bibliography of 152 reports published by contractors of the NRC Office of Nuclear Regulatory Research during the period November 1975 through June 1976 is presented along with abstracts from the Nuclear Safety Information Center computer file. The bibliography has been sorted into the subject categories used by NRC to organize the research program. Within the subject categories, the reports are sorted by contractor organization and then chronologically. A brief description of the NRC research program precedes the bibliography.

The transpiration of CO through the Multihundred Watt (MHW) filter can be described by Fick's first law or as a first order, reversible reaction. From Fick's first law, a ''diffusion'' coefficient of 7.8 x 10/sup -4/ cm.L/sec (L is the average path length through the filter) was determined. For the first order reversible reaction, a rate constant of 0.0058 hr/sup -1/ was obtained for both the forward and reverse reactions (they were assumed to be equal). This corresponds to a half-life of 120 hr. It was also concluded that the rate constants and thus the transpiration rates, which were determined for the test, are smaller than those expected in the IHS. The effect of increasing the number of filters, changing the volumes, and increasing the temperature, changes the rate constant of the transpiration into the PICS to roughly 0.074 hr/sup -1/ (t/sub /sup 1///sub 2// = 9.4 hr) and out of the PICS to 0.84 hr/sup -1/ (t/sub 1/2/ = 0.8 hr). Of the two suggested mechanisms for the generation of CO inside the IHS, the cyclic process requires a much larger rate of transpiration than the process requiring oxygen exchange of CO given off by the graphite. The data …

Activities are reported in research programs devoted to computer operations, isotope separation, low temperature phenomena, separation chemistry, and separation methods. (JRD)

The work reported includes the development of unit processes and equipment for reprocessing of High-Temperature Gas-Cooled Reactor (HTGR) fuel and the design and development of an integrated line to demonstrate the head end of HTGR reprocessing using unirradiated fuel materials. Work is also described on trade-off studies concerning the required design of recycle facilities for the large-scale recycle of HTGR fuels in order to guide the development activities for HTGR fuel recycle.

The following research projects in radiation botany were conducted: mutation breeding of beans and cassava; biological response of coffee plants; and radiosensitivity of tropical plants. In the field of entomology experiments were conducted on radiosterilization of the Mediterranean fruit fly, the coffee leaf miner, the torsalo and the meliaceous shootborer. The following research projects in plant physiology were conducted: physiology of cassava plants; effects of temperature on germination of cacao seeds; physiology of cacao seeds; sulfur metabolism using /sup 35/S; diseases and parasites of banana fruits; the mechanism controlling dwarfism in a radioinduced single gene bean mutant; and the use of wetting agents in foliar nutrition. The following research projects in soil chemistry were conducted: acidity and cation movement in tropical soils; phosphate in soils of the humid tropics; movement, adsorption and desorption of sulfates; free iron and aluminium oxides in tropical soils; mineralization of organic nitrogen in soils on volcanic materials; soil chemical properties of recent volcanic ash; and spatial distribution of the absorbing roots in coffee. Discussions are presented of installation of radiation facilities and collection of rainfall for fallout analysis. (HLW)

As in our earlier work on the sensitized photooxidation of substituted phenylalanines, ring substituents were found to have a marked effect on the photooxidation of uracil. This compound was selected as a typical pyrimidine for detailed studies of the mechanism of photooxidation of molecules of biological importance. The photooxidation of a series of 5-substituted uracils as sensitized by eosin Y, ruthenium bipyridyl, 3-methyl-lumiflavin and methylene blue was studied using oxygen electrode and flash photolysis techniques. Different substituents had very different effects on the rates of photooxidation with a given dye, and some substituents could shift the mechanism from a singlet oxygen pathway to an electron abstraction pathway (or vice versa). A study of the effects of porphyrin structure in relation to photosensitizing characteristics was completed. An examination of the localized selective photooxidation of amino acids in the vicinity of the heme binding site of horseradish peroxidase was made using specifically-bound protoporphyrin IX and other porphyrins as sensitizers. Preliminary studies were carried out on the use of sensitized photooxidation as a tool to study the contribution of histidine-containing crosslinks to the mechanical-thermal properties of mammalian tendon as well as the role of membrane properties in determining the rate and direction of …

The experimental technique for irradiating Nb, Mo, V, and SrCl/sub 2/ samples is outlined. No test results are given. (MOW)

As of July 1975, there were 15 operable nuclear power plants in the Northeast, representing approximately 11 percent of the regional electric generating capability. Construction plans for the next two decades show a strong preference for nuclear units, there being 18 new units under construction and 33 additional units announced. Three projections (scenarios) covering the period from 1976 to 2000 are presented. The Base Case Nuclear Scenario assumes that the construction schedules as of August 31, 1975 are implemented. A Nuclear Moratorium Scenario assumes that no new plants are undertaken after January 1, 1977. Finally, a Maximum Nuclear Growth Scenario postulates a concerted effort to add additional nuclear capacity beginning in 1982, but constrained by the ability of industry to expand the capabilities needed to supply the components and fuel. Appreciable differences in the three scenarios do not appear until about 1985, a consequence of the long lead time in making plans and completing construction. The cumulative incremental costs of the Nuclear Moratorium Scenario postulated in this study exceed $160 billion by the year 2000. Despite the present favorable economics and performance of the nuclear units, and despite the strong preference of the planners for nuclear capacity to meet future …

Significant progress was made on identification and acquisition of optical components for an ultrahigh brightness weakly tunable blue-green beam generator. Limited performance validation of key system design concepts was achieved, and significant progress was made in improved optical design for more efficient generation of ultrahigh brightness, tunable blue-green radiation. These results are detailed.