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Generalized oscillator strengths. Progress report, July 1, 1973--July 1, 1974

Description: Progress is described on research under Contract AT(11-1)3247 and research still to be completed in the period July 1, 1973 to July 1, 1974. The research objectives defined in the original proposal were closely followed. The principal accomplishments during the period were: The introduction of a computer controlled counting system with provision for automatic control and operation of the electron spectrometer currently in use. Electron scattering with excitation of singlet-triplet transitions for helium was studied during the year both to acquire information on collision cross sections and to test a general theory of the abnormally high cross sections for forward scattering found for certain types of transitions. A theoretically predicted minimum in the cross section (at zero scattering angle) was found in a study over the range 100 to 500 eV of the 1/sup 1/S yields 2/sup 3/S transition of helium. Abnormally high cross sections for singlet-triplet transitions at high kinetic energy are predicted when the orbital term symbol is unchanged on excitation. As a test of the theory the X/sup 1/ SIGMA /sup +/ yields b/sup 3/ SIGMA /su p +/ transition in CO was looked for and found at THETA = 0 deg at both 200 and 300 eV thus confirming the theory. New electron scattering studies on both CO and CO/sub 2/ are described. A new method for the calculation of singlet-triplet energy differences from generalized oscillator strengths is described. (auth)
Date: January 1, 1974
Creator: Lassettre, Edwin N.
Partner: UNT Libraries Government Documents Department

Research and development activities waste fixation program. Quarterly progress report, October--December 1973

Description: Two 40-hr nonradioactive spray solidification runs were completed in which both PU-4b and PW-6 reference waste compositions were successfully converted into borosilicate glass. The throughput capacity of the 13-in. diameter spray calciner while processing PW-4b waste is over 38 1/hr with a 700 deg C calciner wall and 24-30 1/hr with a 550 deg C wall. Mechanical agitation increases the capacity of the inconel meiter to over 4.5 l of melt per hour and greatly improves product homogeneity. Both PW-4b and PW-6 reference waste compositions were successfully concentrated in the nonradioactive, wiped film evaporator (WFE) facility. Either waste can be concentrated to approximately 60 wt% total solids in the WFE. For the PW-6 waste, this represents removal of about 80% of the initial liquid present in the waste. Two ceramic melters were built and operated, each using molybdenum electrodes for heating. While the performance of these first melters indicated a number of design and construction problems which need to be resolved, a ceramic-electrode heated melter appears to be a viable alternative to metallic melters. The PW-4b melt composition 72-68 contains finely divided crystallites when large quantities are melted at 1150 deg C. The crystallites were identified as CeO/sub 2/, a spinel and zircon, with CeO/ sub 2/ the predominant species. Several options for eliminating the crystallites include increasing the melt temperature, agitating the melt to prevent crystal settling, modification of the composition to promote CeO/sub 2/ solubility, and reducing the concentration of CeO/sub 2/ in the glass. Helium gas formed by alpha particle emission from actinide nuclides in high-level waste glasses can produce large internal stresses in the glass. A porosity of 0.2% in typical waste glasses, from uranium oxide fuel, may be sufficient to reduce the internal stresses to inconsequential levels by providing sites for gas accumulation. However, for ...
Date: January 1, 1974
Creator: Platt, A. M.
Partner: UNT Libraries Government Documents Department

Dose-to-Man Program progress report, FY 1973

Description: The Dose-to-Man Program at the Savannah River Plant (SRP) was conceived in FY-1972 and operations began in FY-1973. The major objectives of the program are to develop (or adapt), test, and apply comprehensive mathematical models to calculate the radiation dose-to-man from one or more point sources released to the atmosphere or surface waters. These models will be applied to SRP operations; however, the methods are expected to be generally applicable over a large portion of the southeastern United States. A discussion is included of a new meteorological data acquisition program now in operation using a 1200-ft TVtower located near the plant site and seven 200-ft towers to be located onsite in FY-1974. Previously collected meteorological data from the TV-tower were analyzed to show spatial and temporal variation in eddy diffusivity, mesoscale kinetic energy spectra, and dispersion climatology based upon wind-sequencing information. A discussion of a framework for calculation of doseto-man, and a comparison of the Brookhaven National Laboratory (BNL) and Pasquill methods for determining dispersion coefficients are also included. A currert sulfur dioxide survey is discussed which will help verify the calculation techniques for predicting dispersion from heated plumes. (auth)
Date: January 1, 1974
Creator: Crawford, T. V.
Partner: UNT Libraries Government Documents Department

Cover gas seals. 11 - FFTF-LMFBR seal-test program, January-March 1974

Description: The objectives of this program are to: (1) conduct static and dynamic tests to demonstrate or determine the mechanical performance of full-size (cross section) FFTF fuel transfer machine and reactor vessel head seals intended for use in a sodium vapor - inert gas environment, (2) demonstrate that these FFTF seals or new seal configuration provide acceptable fission product and cover gas retention capabilities at LMFBR Clinch River Plant operating environmental conditions other than radiation, and (3) develop improved seals and seal technology for the LMFBR Clinch River Plant to support the national objective to reduce all atmospheric contaminations to low levels.
Date: January 1, 1974
Creator: Kurzeka, W.; Oliva, R. & Welch, F.
Partner: UNT Libraries Government Documents Department

1974 geothermal field tests at the Niland Reservoir in the Imperial Valley of California

Description: The phases of the 1974 geothermal field tests at the Niland Reservoir in the Imperial Valley of California are documented. The following tests are included: separator, steam scrubber, steam turbine, heat exchanger, packed heat exchanger, corrosion, chemical cleaning, and control and instrumentation. (MHR)
Date: January 1, 1974
Partner: UNT Libraries Government Documents Department

Quarterly operating report. Fourth quarter 1974

Description: During the fourth quarter of 1974, the Shippingport Atomic Power Station was shutdown for PWR/LWBR (Pressurized Water Reactor/Light Water Breeder Reactor) Core Conversion. On December 26 while performing a cooldown, following a heat-up test, on operational incident occurred during which the cooldown rate exceeded the 10$sup 0$F/hour allowable limit. A cooldown rate of 13$sup 0$F to 14$sup 0$F/ hour was experienced for a two hour period. After an evaluation of this incident, it was concluded that no deleterious effects to the primary coolant system occurred. Defueling operations continued during the fourth quarter. (auth)
Date: January 1, 1974
Partner: UNT Libraries Government Documents Department

Relationships between fracture toughness and other material properties. Final report

Description: The key experimental and analytical studies which have led to our present understanding of the mechanisms of ductile fracture are reviewed. It is concluded that insufficient progress has been made in the quantitative description of ductile separation mechanisms on a microscale to allow the realistic prediction of fracture toughness from material properties and microstructure. An experimental study of ductile fracture is underway which has the aim of determining the growth rate of voids in known plastic deformation fields as a function of triaxiality of stress and material work-hardening. Novel specimens of particularly well characterized microstructure are utilized.
Date: January 1, 1974
Creator: Perra, M. & Finnie, I.
Partner: UNT Libraries Government Documents Department

Sodium removal, storage, and requalification of components. [LMFBR]

Description: The objectives of this program are to devise, develop, test, and evaluate techniques for sodium removal and storage of test specimens and components, and to expand and refine, by test and analysis, the sodium removal and storage techniques and procedures for use in processing typical LMFBR components.
Date: January 1, 1974
Creator: Gallegos, A.; Shimazaki, T. & Oliva, R.M.
Partner: UNT Libraries Government Documents Department

Fuel-transfer machine-component test. Progress report GFY 1974

Description: The objectives of this program are to conduct the development and testing necessary to produce reliable and adequate handling devices for core components for an LMFBR plant utilizing under-the-shield refueling and reactor vessel cover rotating plugs. Component performance in the following three specific areas of concern will be investigated: (1) a reliable rising stem, vertical motion, in-vessel transfer machine (IVTM) for use in an under-the-shield refueling system with multiple rotating reactor vessel covers, (2) and ex-vessel transfer machine (EVTM) for off-line removal of fuel from the reactor in-vessel storage, and (3) ancillary fuel handling equipment, such as auxiliary handling machines (AHM), floor valves, and core component service equipment.
Date: January 1, 1974
Creator: Kellogg, L. G.; Moody, E. & Jones, C. E.
Partner: UNT Libraries Government Documents Department

Permeability and solubility of gases for FFTF/CRBRP cover-gas-seal materials

Description: The permeability (anti P) and diffusion coefficient (D) of the gases H/sub 2/, Ar, Kr and Xe have been measured in certain elastomer materials of interest to the FFTF/CRBRP Cover Seal Program. These elastomers include Buna N, Buna S, Butyl Rubber, ethylene-propylene polyacrylic, polyurethane and silicone. Measurements were made over the temperature range 100 to 300/sup 0/F. Data for the permeability and diffusion coefficient for these gases in the above elastomer materials are given. The method used also yields data for the solubility of gas in the elastomer; however, these data are less precise than data for anti P and D.
Date: January 1, 1974
Creator: Darnell, A.J.
Partner: UNT Libraries Government Documents Department

Electrical power generation in Wisconsin: the challenge of meeting present needs and future demands. Final report, March 1, 1973--February 28, 1974

Description: Six symposia covering Electrical Power Generation in Wisconsin: the Challenge of Meeting Present Needs and Future Demands were held during the 1973- 74 school year. Each symposium was held in a different area of the state. A generalized program included: Environment Costs and Trades of Enengy Use; Energy and Wisconsin- Today and Tomorrow; and Power Sources for Electricity-Promises and Problems. (MCW)
Date: January 1, 1974
Creator: Lee, L.R.
Partner: UNT Libraries Government Documents Department