Nuclear design of the LLL-GA U/sub 3/Si blanket (open access)

Nuclear design of the LLL-GA U/sub 3/Si blanket

The nuclear design analysis and performance of the blanket for the Pu/sup 239/ producing standard mirror hybrid is discussed. The blanket is based on present day materials and technology. It is designed for peak power density and burnup in the uranium fuel of 500 W/cc and 3 atom percent. The blanket produces 2.0 Mg/yr of Pu-239 (net) from 400 MW fusion (D-T) and depleted uranium and has an average energy multiplication of 11.
Date: May 26, 1978
Creator: Lee, J. D.
Object Type: Article
System: The UNT Digital Library
Tandem Mirror Reactor (open access)

Tandem Mirror Reactor

A reactor based on this concept that produces 1000 MWe consists of a solenoidal magnet about 50 to 100 m long. A cylindrical blanket is used for energy recovery and tritium breeding. Thus the reactor itself is simple and of low technology. The end plugs, however, are of high technology, having the high magnetic fields needed to confine the high-pressure plasma and the high injection energy (0.6 to 1.2 MeV) needed to achieve good magnetic confinement. A low technology, compact, economical hybrid fusion-fission reactor results from injection in the central cell as well as the ends, provided a means can be found to stabilize the end plugs against microinstabilities, particularly in small sizes (plug radius divided by ion gyroradius less than or equal to 10). The Q value is 1.8 and the power is 500 MWe, with 1000 kG of /sup 233/U produced per year. If, on the other hand, the tandem is operated in the two-component mode (i.e., cold tritium plasma electrostatically contained into which a 100-200 keV D/sup 0/ beam is injected), then the end plugs can be stabilized by the outward flowing tritium plasma. Finally, we show that D-D burning tandem reactors appear feasible in large sizes …
Date: May 26, 1978
Creator: Moir, R.W.; Barr, W.L. & Bender, D.J.
Object Type: Article
System: The UNT Digital Library
PWR Blowdown Heat Transfer Separate-Effects Program. Thermal-Hydraulic Test Facility experimental data report for test 167R (open access)

PWR Blowdown Heat Transfer Separate-Effects Program. Thermal-Hydraulic Test Facility experimental data report for test 167R

Reduced instrument responses are presented for Thermal-Hydraulic Test Facility (THTF) test 167R, which is part of the ORNL Pressurized-Water Reactor (PWR) Blowdown Heat Transfer Separate-Effects Program. The objective of the program is to investigate the thermal-hydraulic phenomenon governing the energy transfer and transport processes that occur during a loss-of-coolant accident in a PWR system. Test 167R was conducted to obtain thermal-hydraulic and CHF information in THTF bundle 1 with an intact cold leg. The primary purpose of this report is to make the reduced instrument responses during test 167R available. These are presented in graphical form in engineering units and have been analyzed only to the extent necessary to ensure reasonableness and consistency.
Date: May 26, 1978
Creator: Clemons, V. D.; Hedrick, R. A. & White, M. D.
Object Type: Report
System: The UNT Digital Library
Charge exchange losses during cyclotron acceleration: experiment and theory (open access)

Charge exchange losses during cyclotron acceleration: experiment and theory

Quantitative estimates of charge exchange (CE) losses during acceleration are very important in the design and operation of heavy ion cyclotrons. Such estimates have been made using a vacuum model computer code which was developed to establish vacuum requirements for the MSU superconducting heavy ion cyclotron. This code uses pressure and cross-section data to calculate the radial loss of beam due to charge exchange. Since CE cross sections and radial pressure profiles are not always well known, certain specific measurements have been made using the LBL 88-Inch Cyclotron to provide experimental data needed to test the code. These include measurements of pressure versus radius under vacuum conditions closely approximating those existing during acceleration of /sup 14/N/sup 4 -/ and /sup 40/Ar/sup 8 -/ beams. Beam intensity versus radius data demonstrating transmission losses for three beams are presented. Comparisons with theoretical predictions are given.
Date: May 26, 1978
Creator: Gough, R.A. & Mallory, M.L.
Object Type: Article
System: The UNT Digital Library
Characteristics of tungsten oxide collectors as a function of activation (open access)

Characteristics of tungsten oxide collectors as a function of activation

Addition of minute amounts of oxygen to a thermionic energy converter results in a significant performance improvement. The presence of oxygen reduces the collector work function and decreases the cesium pressure required to obtain a given current density from the emitter. In addition, oxygen additive diodes have the practical benefits of increased interelectrode spacing and improving converter power density and efficiency with polycrystalline electrodes. The motivation for the studies described was to provide insight into the activation processes by characterizing the chemical and physical structures of the tungsten oxide collector surfaces from four thermionic diodes in different states of activation: initial, preactivated, activated, and post-activated. The primary tool for these investigations was Electron Spectroscopy for Chemical Analysis (ESCA) with sputtering capability, which provided chemical composition information as a function of distance through each of the tungsten oxide layers. This study has resulted in several important insights into the activation mechanisms. First, converter performance is correlated with layer thickness and with the oxygen concentration. Second, deconvolution of the ESCA spectra shows that four oxidation states of tungsten (0, +2, +4 and +6) are present at all stages of activation. Third, the cesium distributions indicate that this element is present throughout the …
Date: May 26, 1977
Creator: Balestra, C. L. & Wang, C.
Object Type: Report
System: The UNT Digital Library
Production and Waste Management Division waste status summary, January 1, 1976--March 31, 1976 (open access)

Production and Waste Management Division waste status summary, January 1, 1976--March 31, 1976

Tabulated data are presented for the radioactive waste generated and the status of the waste farms during the first quarter of 1976. (JSR)
Date: May 26, 1976
Creator: Anderson, J. D.
Object Type: Report
System: The UNT Digital Library
Environmental status of the Hanford reservation for July--December 1969 (open access)

Environmental status of the Hanford reservation for July--December 1969

Data are reported on the radioactivity of environmental samples collected from locations within the Hanford plant boundaries during the last six months of 1969. Data are included on: the total alpha activity and content of / sup 90/Sr and tritium in samples of Columbia River water; the total BETA activity of samples of drinking water; the total alpha , BETA , and gamma activity of samples of surface wnters; the total BETA activity and /sup 131/I content of samples of surface air; and the total alpha , BETA , and gamma activity and content of /sup 95/Zr, /sup 106/Ru, /sup 134/Cs, /sup 137/Cs, /sup 140/Ba, /sup 144/Ce, /sup 238/Pu, /sup 239/Pu and /sup 240/Pu of air filter samples. Est imates were made of the average external gamma - radiation exposure rates of personnel. (CH)
Date: May 26, 1970
Creator: Wilson, C.B. & Essig, T.H. (eds.)
Object Type: Report
System: The UNT Digital Library
Maintenance of a multi-cell field reversed mirror reactor (open access)

Maintenance of a multi-cell field reversed mirror reactor

The Field Reversed Mirror Reactor is composed of a horizontal linear chain of cells, each of which requires neutral beam injection. Blanket replacement is achieved by lifting one complete cell module from the reactor and replacing it with a preassembled and tested identical module. Ioffe bar connectors eliminate redundant bus bars. Asymmetric cell design simplifies magnet construction and reduces replacement time. A tapered cylindrical coolant distributor simplifies blanket removal. An evacuated housing surrounds the reactor reducing cell-to-cell sealing problems related to maintenance. Remote couplings are used for coolant and accessories. Hot-cell location and design permits immediate reconditioning or storage of replacement cells.
Date: May 26, 1978
Creator: Neef, W.S. Jr.
Object Type: Article
System: The UNT Digital Library
Transportation energy conservation studies: program plan (open access)

Transportation energy conservation studies: program plan

A program plan for the project is presented. The report contains summary descriptions of tasks and subtasks and schedules and manpower estimates for the project. The four tasks are: provide technical support to the Transportation Energy Conservation Division; analyze the energy savings implications of shifts in shippers' modal choice from truck to rail freight services; examine on an in-depth basis the total energy demands for two heavy rail passenger systems; and develop detailed analytical methods for comprehensive passenger energy economy studies.
Date: May 26, 1978
Creator: unknown
Object Type: Report
System: The UNT Digital Library
LOFCON-LOFT condenser program (open access)

LOFCON-LOFT condenser program

LOFCON is a program developed for the LOFT air condenser system contained in the secondary coolant system. Although the basic theory described herein is general, the program given is not--it is specifically for the LOFT configuration. LOFCON is presented in subroutine form so that it may be easily incorporated into a larger program describing the complete secondary side. Specifically LOFCON was written to be incorporated into the detailed CSMP model of the LOFT secondary coolant system simulation.
Date: May 26, 1978
Creator: Lemmon, E. C. & MacKay, D. B.
Object Type: Report
System: The UNT Digital Library
Digital Computer Programs for Steady-State or Transient Temperature Analysis of Plane and Axisymmetric Bodies by the Finite Element Method. Programs E12202, E12205, E12206, E12207. Engineering Operations Report (open access)

Digital Computer Programs for Steady-State or Transient Temperature Analysis of Plane and Axisymmetric Bodies by the Finite Element Method. Programs E12202, E12205, E12206, E12207. Engineering Operations Report

The problem is to determine the temperature distribution of a complex two-dimensional body with various boundary conditions including radiation effects. The body can consist of several different materials; the material property parameters and boundary conditions can be both temperature and time dependent. The purpose of this report is to describe the numerical procedures and the input instructions for the computer programs which provide the solutions.
Date: May 26, 1972
Creator: Kimura, L.A.; Thomas, E.A. & Yee, F.
Object Type: Report
System: The UNT Digital Library
Small mirror fusion reactors (open access)

Small mirror fusion reactors

Basic requirements for the pilot plants are that they produce a net product and that they have a potential for commercial upgrade. We have investigated a small standard mirror fusion-fission hybrid, a two-component tandem mirror hybrid, and two versions of a field-reversed mirror fusion reactor--one a steady state, single cell reactor with a neutral beam-sustained plasma, the other a moving ring field-reversed mirror where the plasma passes through a reaction chamber with no energy addition.
Date: May 26, 1978
Creator: Carlson, G. A.; Schultz, K. R. & Smith, A. C., Jr.
Object Type: Report
System: The UNT Digital Library