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in creator/contributor: "Bulmer, R. H."

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Tandem Mirror Reactor Systems Code (Version I)

A computer code was developed to model a Tandem Mirror Reactor. Ths is the first Tandem Mirror Reactor model to couple, in detail, the highly linked physics, magnetics, and neutronic analysis into a single code. This report describes the code architecture, provides a summary description of the modules comprising the code, and includes an example execution of the Tandem Mirror Reactor Systems Code. Results from this code for two sensitivity studies are also included. These studies are: (1) to de… more

Date: September 1, 1985

Creator: Reid, R. L.; Finn, P. A.; Gohar, M. Y.; Barrett, R. J.; Gorker, G. E.; Spampinaton, P. T. et al.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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A high-fluence fusion neutron source

A conceptual design of a D-T fusion facility for continuous production of 14-MeV neutron wall loading from 5 to 10 MW/m/sup 2/ at the plasma surface is presented. In this design, D-T neutrons are produced in a linear, two-component plasma formed by neutral beam irradiation of a fully ionized warm plasma target. The beam energy, which is deposited in the center, is transferred to the warm plasma mainly by electron drag and is conducted along the target plasma column to end regions where it is ab… more

Date: February 17, 1988

Creator: Coensgen, F. H.; Casper, T. A.; Correll, D. L.; Damm, C. C.; Futch, A. H.; Logan, B. G. et al.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Projections for a steady-state tokamak reactor based on ITER

The extensions of the physics and engineering guidelines for the ITER device needed for acceptable operating points for a steady-state tokamak power reactor are examined. Non-inductive current drive is provided in steady state by high-energy neutral-beam injection in the plasma core, lower-hybrid slow waves in the outer regions of the plasma and (30%) bootstrap current. Three different levels of extension of the ITER physics/engineering guide-lines, with differing assumptions on the possible pl… more

Date: July 20, 1989

Creator: Devoto, R. S.; Barr, W. L.; Bulmer, R. H.; Campbell, R. B.; Fenstermacher, M. E.; Lee, J. D. et al.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Design and development of neutral beam module components

The Mirror Fusion Test Facility (MFTF) injection system consists of twenty 20 keV start-up, and twenty-four 80 keV sustaining neutral beam source modules. The neutral beam modules are mounted in four clusters equally spaced around the waist of the vacuum vessel which contains the superconducting magnets. A module is defined here as an assembly consisting of a beam source and the interfacing components between that beam source and the vacuum chamber. Six major interfacing components are the subj… more

Date: November 13, 1979

Creator: Holl, P. M.; Bulmer, R. H.; Dilgard, L. W.; Horvath, J. A.; Molvik, A. W.; Porter, G. D. et al.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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A D-T neutron source for fusion materials and technology testing

This report describes a conceptual design of a high-fluence source of 14 MeV D-T neutrons for accelerated testing of materials. The design goal of 10 MW/m/sup 2/ year corresponding to 100 displacements per atom per year is taken to be sufficient for end-of-life tests of candidate materials for a fusion reactor. Such a neutron source would meet a need in the program to develop commercial fusion power that is not yet addressed. In our evaluation, a fusion-based source is preferred for this applic… more

Date: August 1, 1987

Creator: Coensgen, F. H.; Casper, T. A.; Correll, D. L.; Damm, C. C.; Futch, A. H.; Molvik, A. W. et al.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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TIBER: Tokamak Ignition/Burn Experimental Research. Final design report

The Tokamak Ignition/Burn Experimental Research (TIBER) device is the smallest superconductivity tokamak designed to date. In the design plasma shaping is used to achieve a high plasma beta. Neutron shielding is minimized to achieve the desired small device size, but the superconducting magnets must be shielded sufficiently to reduce the neutron heat load and the gamma-ray dose to various components of the device. Specifications of the plasma-shaping coil, the shielding, coaling, requirements, … more

Date: November 1, 1985

Creator: Henning, C. D.; Logan, B. G.; Barr, W. L.; Bulmer, R. H.; Doggett, J. N.; Johnson, B. M. et al.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Mirror Fusion Test Facility magnet system

In 1979, R.H. Bulmer of Lawrence Livermore National Laboratory (LLNL) discussed a proposed tandem-mirror magnet system for the Mirror Fusion Test Facility (MFTF) at the 8th symposium on Engineering Problems in Fusion Research. Since then, Congress has voted funds for expanding LLNL's MFTF to a tandem-mirror facility (designated MFTF-B). The new facility, scheduled for completion by 1985, will seek to achieve two goals: (1) Energy break-even capability (Q or the ratio of fusion energy to plasma … more

Date: September 11, 1981

Creator: VanSant, J. H.; Kozman, T. A.; Bulmer, R. H. & Ng, D. S.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Impact of several reactor features on TF coil design for TPSS

A significant driver of machine size in previous designs was the amount of nuclear shielding placed between the blanket and the toroidal field (TF) coils to minimize the radiation heating and damage in these critical components. Of course the total amount of shielding is not arbitrary; it certainly must adequately suppress radiation outside the plant. However, if all of this shielding were contained inside the TF coils, several parameters (coil size and weight, maximum field at the windings, st… more

Date: March 26, 1986

Creator: Miller, J. R. & Bulmer, R. H.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Status of the mirror-next-step (MNS) study

A study was made to define the features of the experimental mirror fusion device - the Mirror Next Step, or MNS - that will bridge the gap between present mirror confinement experiments and a power-producing reactor. The project goals and organization of the study are outlined, some initial device parameters are described, and the technological requirements are related to ongoing development programs.

Date: September 1, 1979

Creator: Damm, C. C.; Doggett, J. N. & Bulmer, R. H.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Tandem mirror magnet system for MFTF. [MFTF-B]

The Lawrence Livermore Laboratory (LLL) is planning a major extension to the Mirror Fusion Test Facility (MFTF) now under construction at Livermore, CA. This extension brings MFTF to a full tandem mirror configuration, incorporating new ideas for improved plasma confinement. The tandem MFTF is tentatively called MFTF-B. As with most magnetic fusion devices, the confinement coils dominate the overall configuration. This paper concentrates on the MFTF-B magnet configuration, especially field shap… more

Date: November 13, 1979

Creator: Bulmer, R. H.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Tokamak ignition/burn experimental research device

As part of a continuing effort by the Office of Fusion Energy to define an ignition experiment, a superconducting tokamak has been designed with thin neutron shielding and aggressive magnet and plasma parameters. By so minimizing the inner radial dimensions of the tokamak center post, coil, and shielding region, the plasma major radius is reduced with a corresponding reduction in device costs. The peak nuclear-heating rate in the superconducting TF coils is 22 mW/cm/sup 3/, which results in a s… more

Date: April 4, 1985

Creator: Henning, C. D.; Logan, B. G.; Barr, W. L.; Bulmer, R. H.; Doggett, J. N.; Johnston, B. M. et al.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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TIBER II: an upgraded tokamak igntion/burn experimental reactor

We are disIgning a minimum-size Tokamak ignition/Burn Reactor (TIBER II). This design incorporates physics requirements, neutron wall loading and fluence parameters that will make it compatible with a nuclear testing mission. Reactor relevant physics will be tested by using current drive and steady-state operation. Although the design accommodates several current drive options, including neutral beams, the base case uses a combination of lower hybrid and electron-cyclotron radio frequency power… more

Date: June 5, 1986

Creator: Henning, C. D.; Logan, B. G.; Perkins, L. J.; Barr, W. L.; Bulmer, R. H.; Devoto, R. S. et al.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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A non-inductively driven steady state tokamak reactor

The physics and engineering guidelines for the ITER device are shown to lead to viable and attractive operating points for a steady state tokamak power reactor. Non-inductive current drive is provided in steady state by high energy neutral beam injection in the plasma core, lower hybrid slow waves in the outer regions of the plasma and bootstrap current. Plasma gain Q (/equivalent to/fusion power/input power) in excess of 20 and average neutron wall loading, <GAMMA> approx. 2.0 MW/m/sup 2/ are … more

Date: September 20, 1988

Creator: Fenstermacher, M. E.; Devoto, R. S.; Bulmer, R. H.; Lee, J. D.; Miller, J. R. & Schultz, J.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Tandem mirror next step conceptual design

A study was made to define the features of the experimental mirror fusion device - The Tandem Mirror Next Step, or TMNS - that will bridge the gap between present mirror confinement experiments and a power-producing reactor. We outline the project goals, describe some initial device parameters, and relate the technological requirements to ongoing development programs.

Date: October 14, 1980

Creator: Doggett, J. N.; Damm, C. C. & Bulmer, R. H.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Physics conceptual design for the MFTF-B transition coil

The physics constraints related to finite-..beta.. equilibria, ..beta.. limits due to curvature-driven MHD modes, and ion transport in the central cell. These physics constraints had to be satisfied subject to certain non-physics constraints. Principal among these were the geometric and structural features of the existing MFTF-B magnet set and the required access for neutral beams for pumping. These constraints and their origins are discussed.

Date: August 7, 1982

Creator: Baldwin, D. E. & Bulmer, R. H.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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A non-inductively driven tokamak reactor based on ITER

The physics and engineering guidelines for the ITER device are shown to lead to viable physics operating points for a steady state tokamak power reactor. Non-inductive current drive is provided in steady state by high energy neutral beam injection in the plasma core, lower hybrid slow waves in the outer regions of the plasma and bootstrap current. Plasma gain Q(/equivalent to/fusion power/input power) in excess of 20 and average neutron wall loading, <GAMMA> approx. 2.0 MW/m/sup 2/ are predicte… more

Date: December 1, 1988

Creator: Fenstermacher, M. E.; Devoto, R. S.; Bulmer, R. H.; Lee, J. D.; Miller, J. R. & Schultz, J. H.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Structural and thermal requirements for the tandem-mirror fusion-test-facility magnet system

Structural requirements for the magnet system include unique spatial constraints and materials restrictions to meet the operational needs of the unusual configuration. All of the magnets are liquid helium cooled which represents about 1500 tonnes of 4.5 K structure in the vacuum environment of the large vessel. Magnet support structures must satisfy complex load conditions, including electromagnetic (both normal-operating and fault conditions) and seismically induced. Improved plasma confinemen… more

Date: February 6, 1981

Creator: VanSant, J. H. & Bulmer, R. H.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

TIBER: tokamak ignition/burn experimental research

As part of a continuing effort by the Office of Fusion Energy to define an ignition experiment, a superconducting tokamak has been designed with thin neutron shielding and aggressive magnet and plasma parameters. By so minimizing the inner radial dimensions of the tokamak center post, coil, and shielding region, the plasma major radius is reduced, with a corresponding reduction in device costs. The peak nuclear-heating rate in the superconducting TF coils is 22 mW/cmT, which results in a steady… more

Date: November 1985

Creator: Henning, C. .; Logan, B. G.; Barr, W. L.; Bulmer, R. H.; Doggett, J. N.; Johnston, B. M. et al.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Preliminary design of a Tandem-Mirror-Next-Step facility

The Tandem-Mirror-Next-Step (TMNS) facility is designed to demonstrate the engineering feasibility of a tandem-mirror reactor. The facility is based on a deuterium-tritium (D-T) burning, tandem-mirror device with a fusion power output of 245 MW. The fusion power density in the central cell is 2.1 MW/m/sup 3/, with a resultant neutron wall loading of 0.5 MW/m/sup 2/. Overall machine length is 116 m, and the effective central-cell length is 50.9 m. The magnet system includes end cells with yin-ya… more

Date: December 18, 1980

Creator: Damm, C. C.; Doggett, J. N. & Bulmer, R. H.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Vacuum analysis and design for the MFTF-B Tandem Magnetic Fusion Experiment

Three vacuum vessels comprise the vacuum envelope of MFTF-B. The design specifications are given for each. (MOW)

Date: October 13, 1980

Creator: Pittenger, L. C.; Bulmer, R. H.; Lane, M. A.; Margolies, D. S.; Valby, L. E. & Vepa, K.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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ETR/ITER systems code

A tokamak systems code capable of modeling experimental test reactors has been developed and is described in this document. The code, named TETRA (for Tokamak Engineering Test Reactor Analysis), consists of a series of modules, each describing a tokamak system or component, controlled by an optimizer/driver. This code development was a national effort in that the modules were contributed by members of the fusion community and integrated into a code by the Fusion Engineering Design Center. The c… more

Date: April 1, 1988

Creator: Barr, W. L.; Bathke, C. G.; Brooks, J. N.; Bulmer, R. H.; Busigin, A.; DuBois, P. F. et al.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Toward a design for the ITER plasma shape and stability control system

A design strategy for an integrated shaping and stability control algorithm for ITER is described. This strategy exploits the natural multivariable nature of the system so that all poloidal field coils are used to simultaneously control all regulated plasma shape and position parameters. A nonrigid, flux-conserving linearized plasma response model is derived using a variational procedure analogous to the ideal MHD Extended Energy Principle. Initial results are presented for the non-rigid plasma… more

Date: July 1, 1994

Creator: Humphreys, D. A.; Leuer, J. A.; Kellman, A. G.; Haney, S. W.; Bulmer, R. H.; Pearlstein, L. D. et al.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Tokamak Physics Experiment poloidal field design

The Tokamak Physics Experiment (TPX) will have a poloidal field system capable of full inductive operation poloidal for approximately a 20-s flattop and, with superconducting toroidal and poloidal field coils and non-inductive current drive, it will be capable of true steady-state operation. The poloidal field design is based on the ideal MHD equilibrium model as implemented in the TEQ code developed at LLNL. The PF coils are arranged in an up-down symmetric configuration, external to the TF co… more

Date: October 6, 1993

Creator: Bulmer, R. H.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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TPX magnet system status

No Description Available.

Date: August 17, 1994

Creator: Bulmer, R. H.; Chaplin, M. R. & Lang, D. D.

Item Type: Article

Partner: UNT Libraries Government Documents Department