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Year
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TFTR Motor Generator
A general description is given of 475 MVA pulsed motor generators for TFTR at Princeton Plasma Physics Laboratory. Two identical generators operating in parallel are capable of supplying 950 MVA for an equivalent square pulse of 6.77 seconds and 4,500 MJ at 0.7 power factor to provide the energy for the pulsed electrical coils and heating system for TFTR. The description includes the operational features of the 15,000 HP wound rotor motors driving each generator with its starting equipment and cycloconverter for controlling speed, power factor, and regulating line voltage during load pulsing where the generator speed changes from 87.5 to 60 Hz frequency variation to provide the 4,500 MJ or energy. The special design characteristics such as fatigue stress calculations for 10/sup 6/ cycles of operation, forcing factor on exciter to provide regulation, and low generator impedance are reviewed.
Date:
January 1, 1977
Creator:
Murray, J. G.; Bronner, G. & Horton, M.
Object Type:
Article
System:
The UNT Digital Library
LASL thermochemical hydrogen program status on October 31, 1977. [Cycles using sulfuric acid as an intermdiate]
The LASL Hydrogen Program is continuing its investigation of practical schemes to decompose water thermochemically for hydrogen production. Efforts were and are being devoted to process improvements in cycles that use sulfuric acid as an intermediate. Sulfuric acid-hydrogen bromide cycles are being studied as a means of overcoming the heat penalty in drying acid solutions. An alternate approach involves the use of insoluble bismuth sulfate that is precipitated from acid solution. Preliminary energy balances indicate a significant increase in cycle efficiency for both these options.
Date:
January 1, 1977
Creator:
Cox, K.E. & Bowman, M.G.
Object Type:
Article
System:
The UNT Digital Library
Radiation shield design for LMFBR spent-fuel shipping casks
Previous analyses have examined a limited number of the alternatives available for designing an LMFBR spent-fuel shipping cask (SFSC) using a non-volatile neutron shield; i.e., a neutron shield which will not be lost in an accident involving a fire. The present study extends the scope of these hypothetical designs to include combinations of volatile and non-volatile neutron shield materials.
Date:
January 1, 1977
Creator:
Dupree, S. A.
Object Type:
Article
System:
The UNT Digital Library
Monte-Carlo approach to the generation of adversary paths
This paper considers the definition of a threat as the sequence of events that might lead to adversary success. A nuclear facility is characterized as a weighted, labeled, directed graph, with critical adversary paths. A discrete-event, Monte-Carlo simulation model is used to estimate the probability of the critical paths. The model was tested for hypothetical facilities, with promising results. (DLC)
Date:
January 1, 1977
Creator:
unknown
Object Type:
Article
System:
The UNT Digital Library
Design approaches for enhancing the engineering feasibility of tokamak power reactors
The design approach developed in the ORNL Fusion Power Demonstration Study is reviewed. The design concepts having greatest impact on reactor feasibility by the application of current or near term technology are described briefly. These are: blanket structural material, blanket coolant, power conversion system, and pulsed electrical system. Concepts relative to the approach taken to simplify the overall reactor design are listed. (MHR)
Date:
January 1, 1977
Creator:
Shannon, T.E. & Steiner, D.
Object Type:
Article
System:
The UNT Digital Library
Thermoelectric effect in a nonequilibrium superconductor
Initial results are reported showing experimental evidence for a pair-quasiparticle electrochemical potential difference in a superconductor in a temperature gradient. This potential diverges at low temperature and, within the resolution of the data, seems to approach a constant value at T/sub c/. The data can be used to extract a value for the thermal transport current of normal excitations in the superconductor.
Date:
January 1, 1977
Creator:
Falco, C.M.
Object Type:
Article
System:
The UNT Digital Library
Analysis of angular dependent Auger spectroscopy (ADAS) based on a quasiatomic model. [Partial waves]
Calculated results are presented which are in good agreement with published M/sub 2/, /sub 3/VV Cu (100) ADAS data. The calculations are based on a quasiatomic model where each individual Auger emission is a partial wave of definite (l,m) character, but (l,m) may differ from emission to emission. The (l,m) emission weights have been estimated by fitting the data with a linear combination of calculated intensities for (l,m) up to l = 5. It is found that surprisingly few (l,m) values are necessary to obtain reasonable fits to the data, and the best fits occur for combinations of (l,m) intensities in which the l = 3 waves were most heavily weighted.
Date:
January 1, 1977
Creator:
Davis, H.L.
Object Type:
Article
System:
The UNT Digital Library
Software package as an information center product. [Activities of Argonne Code Center]
The Argonne Code Center serves as a software exchange and information center for the U.S. Energy Research and Development Administration and the Nuclear Regulatory Commission. The goal of the Center's program is to provide a means for sharing of software among agency offices and contractors, and for transferring computing applications and technology, developed within the agencies, to the information-processing community. A major activity of the Code Center is the acquisition, review, testing, and maintenance of a collection of software--computer systems, applications programs, subroutines, modules, and data compilations--prepared by agency offices and contractors to meet programmatic needs. A brief review of the history of computer program libraries and software sharing is presented to place the Code Center activity in perspective. The state-of-the-art discussion starts off with an appropriate definition of the term software package, together with descriptions of recommended package contents and the Carter's package evaluation activity. An effort is made to identify the various users of the product, to enumerate their individual needs, to document the Center's efforts to meet these needs and the ongoing interaction with the user community. Desirable staff qualifications are considered, and packaging problems, reviewed. The paper closes with a brief look at recent developments and …
Date:
January 1, 1977
Creator:
Butler, M.K.
Object Type:
Article
System:
The UNT Digital Library
Response of the Asiatic clam, Corbicula manilensis, to gamma radiation
When heat exchangers for reactors were plugged by the Asiatic clam, acute gamma radiation was considered as a possible control. Clams were collected and sorted by size; during irradiation the clams were submerged in natural water. Clams of both sizes survived large doses with no radiation damage evident in 30 days. Mortality rose steeply at doses of 2.4 x 10/sup 4/ Rad and above; smaller clams showed a greater resistance than large ones. The feasibility of using periodic exposure to gamma radiation as a means for controlling corbicula infestations is discussed. (HLW)
Date:
January 1, 1977
Creator:
Tilly, L. J.; Corey, J. C. & Bibler, N. E.
Object Type:
Article
System:
The UNT Digital Library
TNS design space exploration has brought us a large step closer to realizable reactor
Some technological justifications for the TNS (technological next step) are outlined. Programmatic diagrams are included. (MOW)
Date:
January 1, 1977
Creator:
Roberts, M.
Object Type:
Article
System:
The UNT Digital Library
Low-level x-irradiation of the brain during development morphological, physiological, and behavioral consequences. Final report, September 1, 1976--August 31, 1977
Morphological research was continued in the following areas: glial recovery patterns in the rat corpus callosum after x-irradiation during infancy; the prenatal development of the deep nuclei and cortex of the cerebellum; the prenatal development of the inferior olive, pontine gray and the precerebellar reticular nuclei; and the postnatal development of the olfactory bulb. In these studies autoradiography and x-irradiation were among the experimental techniques utilized. The behavioral studies, all of which are still in progress, are concerned with the effects of different schedules of postnatal x-irradiation of the cerebellum, and the effects of x-irradiation of the olfactory bulb. A list is included of 14 publications that report results in detail.
Date:
January 1, 1977
Creator:
Altman, J.
Object Type:
Report
System:
The UNT Digital Library
Regenerative process for desulfurization of high temperature combustion and fuel gases. Quarterly progress report No. 5, April 1--June 30, 1977
The sulfation rate of reagent-grade monocalcium silicate is of the same order of magnitude as that of limestone and higher than that of reagent-grade calcium oxide. It has been confirmed that the sulfated monocalcium silicate is more regenerable than the sulfated lime, i.e., the regeneration rate is higher with the silicate. X-ray diffraction and IR absorption results indicate that silica is chemically bonded to the calcium sulfate in the sulfated calcium silicate. Construction of a micro-pilot rotary kiln for regeneration of lime from the sulfated lime has been completed. The Brookhaven processes for regeneration using fly ash from FBC will be tested with this device. Design and construction of a micro-combustor which will be used to test the regenerated lime are underway. Studies on sulfation of lime continue. Sodium chloride, although catalyzing the sulfation rate, yields too much chloride in the gas phase (60 percent NaCl at 900/sup 0/C), which can chlorinate the metals and metal oxides in the combustor. The catalysis by Fe/sub 2/O/sub 3/ and/or coal ash has been established and its mechanisms have been studied. Effects of the calcination conditions on sulfation are being studied. A process flow diagram for producing commercial strength sulfuric acid from regenerator …
Date:
January 1, 1977
Creator:
Steinberg, M & Yang, R T
Object Type:
Report
System:
The UNT Digital Library
First in-core molten fuel pool experiment. [LMFBR]
If during a LMFBR accident a fuel debris bed is not adequately cooled by overlying sodium and dryout occurs, then the fuel would heat up and melt. Molten fuel pools are of concern due to their potential for ablation of the supporting structure and possible penetration of the reactor vessel. The major goal of the molten fuel pool program has been to develop a versatile experiment in which heat flux and structural ablation could be studied using real materials under typical temperature and heating conditions. This has now been accomplished, using the Annular Core Pulse Reactor (ACPR) to fission heat enriched UO/sub 2/. In the first experiment conducted, a small portion of a 0.834 kg UO/sub 2/ sample was melted, and temperature data were recorded to above the melting point of the UO/sub 2/ using ultrasonic thermometry.
Date:
January 1, 1977
Creator:
Plein, H.G. & Carlson, G.A.
Object Type:
Article
System:
The UNT Digital Library
Ceramic processing of boron nitride insulators
Fuel pin simulators (FPS) are the prime elements of several test facilities at the Oak Ridge National Laboratory (ORNL). These experimental facilities are used to conduct out-of-reactor thermal-hydraulic and mechanical interaction safety tests for both light-water and breeder reactor programs. The FPS units simulate the geometry, heat flux profiles, and operational capabilities of a reactor core element under steady-state and transient conditions. They are subjected to temperatures as high as 1600/sup 0/C (2900/sup 0/F) and power levels as high as 57.5 kW/m (17.5 kW/ft) as well as severe thermal stresses during transient tests. The insulating material in the narrow annulus between the heating coil and the FPS sheath is subjected to very rigorous conditions. Accuracy of the reactor safety test information and validity of the test data depend on the heat flux uniformity under all test conditions and on the reliable operation of all fuel pin simulators and their internal thermocouples. Boron nitride (BN), because of its high degree of chemical inertness combined with its relatively unique properties of high thermal conductivity and low electrical conductivity, is the most suitable insulating material for FPS. The important BN properties, thermal conductivity and electrical resistance, are strongly influenced by crystallite orientation and …
Date:
January 1, 1977
Creator:
Morgan, C.S. & McCulloch, R.W.
Object Type:
Article
System:
The UNT Digital Library
Statistical problems arising from simulation of a high-throughput nuclear facility
Shortages in traditional energy sources, such as oil and natural gas, have placed greater emphasis on alternative fuel sources. With an already developed technological base and cost history, nuclear power is an attractive option. However, the public's attitude toward recent terrorism has generated strong demands for improved safeguards measures to deter, detect, and protect against diversion of special nuclear material (SNM). To encourage improved safeguards accountability, the Nuclear Regulatory Commission (NRC) has been considering the use of performance oriented regulations to supplement those currently used. A study, sponsored by NRC/Office of Standards Development, was conducted to evaluate the controllable unit approach (CUA) to meeting performance oriented regulations. The study results are used to provide the NRC with a methodology that systematically and iteratively compares the actual situation to the need before additions or refinements are imposed. And because the existing or proposed system is mathematically modeled, modifications to the process for any reason can be tested quickly for their effect on material control before implementation. A summary flow diagram of the CUA methodology is shown and described.
Date:
January 1, 1977
Creator:
Seabaugh, P. W.; Rogers, D. R.; Woltermann, H. A.; Fushimi, F. C. & Ciramella, A. F.
Object Type:
Article
System:
The UNT Digital Library
Safeguards planning in a plant design process
The safeguards efforts for the partitioning fuel cycle are considered. Included in the discussion are the organization of the safeguards study, the development of safeguards criteria, the expression of these criteria as requirements for facility design, and some preliminary details of the implementation of these requirements in facility and process layout. (LK)
Date:
January 1, 1977
Creator:
Heinrich, L.A.
Object Type:
Article
System:
The UNT Digital Library
Advantages of iron core in a tokamak
A quantitative comparison of the iron core vs air core concepts was carried out on a preliminary basis by using a representative tokamak reactor design with the following self-consistent reference parameters. In the area of plasma engineering, poloidal field and MHD equilibrium considerations with an unsaturated iron core is discussed. The question of proper poloidal field coils to maintain D-shaped plasmas of relatively high anti ..beta.. (7%) with a saturated iron core is also discussed. Estimates of the required iron core size, volt seconds, magnetic flux and its influence on force loading on the superconducting toroidal field coils are shown. Conceptual designs of the mechanical structure of an iron core device are presented. Favorable impacts on the OH power supply cost and complexity are indicated.
Date:
January 1, 1977
Creator:
Bettis, E. S.; Ballou, J. K.; Becraft, W. R.; Peng, Y. K. M. & Watts, H. L.
Object Type:
Article
System:
The UNT Digital Library
Electrolysis based hydrogen storage systems. Annual report, January 1, 1976--December 31, 1976
This report describes work completed during the period January 1, 1976 to December 31, 1976, on an ERDA-sponsored program aimed at improvement in the cost and efficiency of electrolytic hydrogen production and development of the technique of using metal hydrides for hydrogen storage for stationary and transportation applications. The work on electrolytic hydrogen production includes work on advanced barrier materials for alkaline cells, studies of nickel alloy based and oxide catalysts for oxygen evolution. Related work on the program involving the H/sub 2/--Cl/sub 2/ electrochemical cell for energy storage is described. Work on hydrogen storage subsystems involving storage reservoir designs for the Hydrogen Technology Advanced-Component Test System (HYTACTS), engineering and metal hydride material test beds and tests of candidate container materials is presented. Progress on the development of new metal hydride materials and tailoring and testing of new alloy systems is summarized. This work emphasizes improvement in the initial activation step, high-cycle test of selected materials and the physical characteristics of cycled materials. The efforts on natural gas supplementation, hydrogen storage systems analysis and the project management of the ERDA Hydrogen Program by BNL are summarized.
Date:
January 1, 1977
Creator:
Salzano, F J
Object Type:
Report
System:
The UNT Digital Library
Resistive requirements for the vacuum wall of a Tokamak Fusion Reactor
The effect of having a conducting vacuum wall, instead of one with a flux breaker, has been analyzed from a multi-disciplinary standpoint. There is a good indication that a conducting wall will be tolerable. The most serious problems seem to be in designing an acceptable initiation-trimming coil system and in designing a vacuum wall that can withstand the pressure and heat loads following a plasma dump. There appear to be several promising design approaches for the vacuum wall that can achieve a fairly high resistance and may satisfy the latter constraints.
Date:
January 1, 1977
Creator:
Brooks, J. N.; Ehst, D.; Harkness, S. D.; Norem, J.; Stevens, H. & Turner, L.
Object Type:
Article
System:
The UNT Digital Library
Deposition of uniform aluminum films on Kapton laminates by electron beam evaporation
Aluminum films 10 ..mu..m thick with a thickness uniformity in the one percent range have been obtained on the Kapton surface of a laminated substrate consisting of Kapton/Kapton/aluminum foil bonded with a thermosetting adhesive. The processing of the substrates before deposition necessary to obtain reasonable deposition cycle times and a minimal amount of deposition system contamination was developed. The laminated substrates required bakeouts both at atmosphere and in high vacuum prior to deposition to permit evaporation at a pressure of 0.1 mPa (1 x 10/sup -6/ torr). The deposited films exhibited a high specular reflectance and were thus mirror-like in appearance. Film resistivity was within 10 percent of that of bulk aluminum, and the films displayed a strong (111) fiber texture.
Date:
January 1, 1977
Creator:
Sherman, D.M.
Object Type:
Article
System:
The UNT Digital Library
Studies of the lattice dynamics and phase transitions in 1T--TiSe/sub 2/ and 2H--TaSe/sub 2/
Neutron inelastic scattering measurements have been carried out to study the lattice dynamics associated with the 200K phase transition in the layered semimetal IT--TiSe/sub 2/. Dispersion relations for many modes with energies below 20 MeV have been measured. The soft transverse mode, which is involved in the transition, has been located and its temperature dependence examined. These results will be compared to data previously reported on the lattice dynamics of the charge-density-wave transition in 2H--TaSe/sub 2/.
Date:
January 1, 1977
Creator:
Moncton, D.E.; Di Salvo, F.J. & Axe, J.D.
Object Type:
Article
System:
The UNT Digital Library
Recent operational history of the new Sandia Pulsed Reactor III (SPR III)
The Sandia Pulsed Reactor III (SPR III) is a fast-pulse research reactor which was designed and built at Sandia Laboratories and achieved criticality in August 1975. The reactor is now characterized and is in an operational configuration. The core consists of 18 fuel plates (258 kg fuel mass) of fully enriched uranium alloyed with 10 wt.% molybdenum. It is arranged in an annular configuration with an inside diameter of 17.78 cm, an outside diameter of 29.72 cm, and a height of 35.9 cm. The reactor core uses reflectors of copper and aluminum for control and an external bolting arrangement to secure the fuel plates. SPR III and SPR II are operated on an interchangeable basis using the same facility and control system. As of June 1977, SPR III has had over 240 operations with core temperatures up to 541/sup 0/C.
Date:
January 1, 1977
Creator:
Schmidt, T. R.; Estes, B. F. & Reuscher, J. A.
Object Type:
Article
System:
The UNT Digital Library
Wall power measurements of impurity radiation in ORMAK
Time-resolved measurements of the power loss to the ORMAK liner were made using a pyroelectric detector. These measurements indicate that a large, relatively constant fraction (approximately 60 percent) of the electron power input is lost to the liner, rather than to the limiter, over a wide range of input powers (ohmic heating + neutral beam injection) and plasma conditions, and for most of the discharge duration. Most of this energy loss is due to impurity radiation peaked at about a third of the limiter radius and is time-correlated with gross plasma fluctuations, internal disruptions, and related spectroscopic impurity signals.
Date:
January 1, 1977
Creator:
Bush, C. E. & Lyon, J. F.
Object Type:
Article
System:
The UNT Digital Library
System engineering and design of a pulsed homopolar generator power supply for the Texas Experimental Tokamak
The design of a homopolar generator power supply for the Texas Experimental Tokamak (TEXT) is presented. Four series-connected disk type homopolar machines serve as inertial energy storage and conversion devices to supply 50 to 70 MW peak power to the toroidal field coil and ohmic heating coil circuits. The system is nominally operated at 150 MJ, 430 V to provide a 0.5 sec flat top, 160 kA TF current pulse and a 0.3 sec, 10 kA OH current pulse every 2.0 min on a continuous basis. The system has a maximum capacity of 200 MJ at a maximum open circuit voltage of 500 V. The homopolar machine design is described.
Date:
January 1, 1977
Creator:
Bird, W. L.; Grant, G. B.; Weldon, W. F.; Rylander, H. G. & Woodson, H. H.
Object Type:
Article
System:
The UNT Digital Library