Most of the procedures and techniques described were developed over the past three years. Starting in late 1976, development began on high-accuracy computer codes for electromagnetic field and force analysis. This effort resulted in completion of a family of computer programs called MAGIC (MAGnetic Integration Calcaultion). Included in this group of programs is a post-processor called POSTMAGIC that links MAGIC to GDSAP (General Dynamics Structural Analysis Program) by automatically transferring force data. Integrating these computer programs afforded us the capability to readily analyze several different conditions that are anticipated to occur during tokamak operation. During 1977 we initiated the development of the CONVERT program that effectively links our THERMAL ANALYZER program to GDSAP by automatically transferring temperature data. The CONVERT program allowed us the capability to readily predict thermal stresses at several different time phases during the computer-simulated cooldown and warmup cycle. This feature aided us in determining the most crucial time phases and to adjust recommended operating procedure to minimize risk.

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During the heat treatment step of High Temperature Gas-Cooled Reactor (HTGR) fuel beads, the /sup 233/U-loaded fuel beads are exposed to temperatures as high as 1700/sup 0/C. Since /sup 233/U fuel beads unavoidably contain a small percentage of /sup 232/U, decay products of /sup 232/U might be released during the heat treatment step. To avoid shielding requirements, experiments were conducted using /sup 232/Th-loaded fuel beads rather than /sup 232/U-loaded fuel beads. Decay products of /sup 232/U and /sup 232/Th are the same after /sup 228/Th. Experimental data were obtained by monitoring the 583 and 2614 keV gamma emissions of /sup 208/Tl. Computer simulations of the decay process and experimental data were used to infer what relative amount of the daughter products was removed. The carbonization step (300 to 500/sup 0/C) has an effect on the loss of daughter products in the conversion step. Using uncarbonized fuel beads, approximately 50 percent of /sup 220/Rn was removed at 300/sup 0/C and approximately 20 percent of /sup 220/Rn was removed at 200/sup 0/C. At most, 5 percent of /sup 220/Rn was removed from uncarbonized beads at 25/sup 0/C. Marginal /sup 220/Rn loss was detected at 100/sup 0/C using pre-carbonized beads. At 1400/sup 0/C, …

This 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 1974 through 1975. The bibliography consists of approximately 1554 abstracts covering early 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 for completeness.

The preliminary results of an unsteady three-dimensional potential flow analysis of a five-liter flask air injection experiment (small-scale model simulation of a nuclear reactor steam condensation system) are presented. The location and velocity of the free water surface in the flask as a function of time are determined during pipe venting and bubble expansion processes. The analyses were performed using an extended version of the NASA-Ames Three-Dimensional Potential Flow Analysis System (POTFAN), which uses the vortex lattice singularity method of potential flow analysis. The pressure boundary condition at the free water surface and the boundary condition along the free jet boundary near the pipe exit were ignored for the purposes of the present study. The results of the analysis indicate that large time steps can be taken without significantly reducing the accuracy of the solutions and that the assumption of inviscid flow should not have an appreciable effect on the geometry and velocity of the free water surface. In addition, the computation time required for the solutions was well within acceptable limits.

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To minimize the radiological risk from the operation of a waste management system for the safe disposal of high-level waste, performance characteristics of the solidified waste form must be specified. The minimum waste form characteristics that must be specified are the radionuclide volatilization fraction, airborne particulate dispersion fraction, and the aqueous dissolution characteristics. The results indicate that the pre-emplacement environs are more limiting in establishing the waste form performance criteria than the post-emplacement environs. The actual values of expected risk are sensitive to modeling assumptions and data base uncertainties. The transportation step appears to be the most limiting in determining the required performance characteristics.

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Methods used to obtain evaluated neutron interaction and photon production data for /sup 238/U are described. (auth)

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EDIT allows the user to edit or create text, either interactively or in the batch mode. The text may be a source program, program data, or documents. Special provisions permit the creation or editing of APT source-language programs. EDIT processes ASCII files from any accessible Data Director library and outputs files to any such library as specified by the user.

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Soil accumulation has been the most significant factor in the degradation of the output of photovoltaic modules used in experimental solar power generating systems. One method of measuring dirt accumulation and the subsequent power loss is to return photovoltaic modules to the laboratory for thorough examination. The use of a Glossmeter as a practical alternative to laboratory examination in making quantitative measurements of dirt accumulation on PV modules is described. Of particular value for in-situ measurements, this instrument has been used successfully to monitor dirt build-up on the front surfaces of several types of modules before and after cleaning. Surface gloss has been correlated with peak power and short-circuit current. It has also been used as an indication of the extent of dirt accumulation and the effectiveness of a cleaning process. Data obtained from Glossmeter readings taken on photovoltaic modules with over a year's exposure at photovoltaic field test sites in Nebraska; New York City; and MIT, Cambridge, are presented.

The natures of compressional (P) waves that originate in the crust, propagate in the crust and upper mantle, and are observed as Pg, Pn, and anti P waves at regional distances are examined. The discussion includes the observed variations of amplitude with epicentral distance for these waves as well as an estimate of values for the specific dissipation function Q/sub ..cap alpha../ in different regions. Studies were made on theoretical source and propagation functions for direct, reflected, and head waves as approximations for the observed Pg, anti P, and Pn, respectively. It was concluded that the classical (critically refracted) head wave is not very significant in regional observations, and that the related interference head wave and diving wave are more likely observed as Pn. Using an assumed seismic noise spectrum and the constant Q/sub ..cap alpha../ model for seismic attenuation, relations were derived for the frequencies corresponding to maximum signal-to-noise ratio for the classical and interference head waves and for the direct, reflected, and diving waves. The relations among seismic frequency, epicentral distance, anelastic attenuation, and explosion yield are illustrated for a simple source and propagation model.

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The objectives of the program are to conduct tests that will characterize the behavior of sodium oxide, fuel, fission product, and other aerosols as they might be generated by various postulated LMFBR accidents; determine by analysis and confirm by experiment the generation and transport of these aerosols with respect to source (location, type, and configuration), for the entire course of events associated with real and hypothetical accident conditions; and conduct tests that will determine the effect of molten fuel on reactor structural or sacrificial material.

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