J. Schmidt

Villanova University

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Co-Authors

C. Kessel

Oak Ridge National Laboratory

G.H. Neilson

Princeton Plasma Physics Laboratory

W. Reiersen

Princeton Plasma Physics Laboratory

R.J. Goldston

Princeton Plasma Physics Laboratory

S.C. Jardin

Princeton Plasma Physics Laboratory

N. Pomphrey

Princeton Plasma Physics Laboratory

P. H. Rutherford

Liverpool Heart and Chest Hospital

Y.K.M. Peng

ENN (China)

J. Sinnis

Los Alamos National Laboratory

D.J. Strickler

Oak Ridge National Laboratory

Cooperative Institutions

Princeton Plasma Physics Laboratory

323

Princeton University

261

Oak Ridge National Laboratory

197

Fusion Academy

134

Fusion (United States)

127

Lawrence Livermore National Laboratory

114

General Atomics (United States)

112

Massachusetts Institute of Technology

University of Wisconsin–Madison

Korea Basic Science Institute

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Possible neutral beam requirements for TFTR upgrades

B. Prichard R. Little D.E. Post J. Schmidt

A discussion is provided of possible neutral beam requirements and constraints for a TFTR upgrade. The time scale is the early 80s and beams of 250 keV D/sup 0/, probably using 65 ampere negative ion sources, existing power supplies and vacuum enclosures would be required. (MHR)

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Physics Regimes in the Fusion Ignition Research Experiment (FIRE)

D. M. Meade S.C. Jardin C. Kessel M. Ulrickson J.H. Schultz

Burning plasma science is recognized widely as the next frontier in fusion research. The Fusion Ignition Research Experiment (FIRE) is a design study of a next-step burning plasma experiment with the goal of developing a concept for an experimental facility to explore and understand the strong nonlinear coupling among confinement, magnetohydrodynamic (MHD) self-heating, stability, edge physics, and wave-particle interactions that is fundamental to fusion plasma behavior. This will require plasmas dominated by alpha heating (Q greater than or equal to 5) that are sustained for a duration comparable to characteristic plasma timescales (greater than or equal to 10) tau(subscript ''E''), approximately 4 tau(subscript ''He''), approximately 2 tau(subscript ''skin''). The work reported here has been undertaken with the objective of finding the minimum size (cost) device to achieve these physics goals.

10.2172/787681

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Citations (4)

Electrical energy requirements for ATW and fusion neutrons

D.L. Jassby J. Schmidt

This note compares the electrical energy requirements of accelerator (ATW) and fusion plants designed to transmute nuclides of fission wastes. Both systems use the same blanket concept but for each source neutron the fusion system must utilize one blanket neutron for tritium breeding. The ATW and fusion plants are found to have the same electrical energy requirement per available blanket neutron when the blanket coverage is comparable and fusion Q {approx} 1, but the fusion plant has only a fraction of the energy requirement when Q {much{underscore}gt} 1. If the blanket thermal energy is converted to electricity, the fusion plant and ATW have comparable net electrical energy outputs per available neutron when Q {>=} 2.

Nuclide

Fusion power

Nuclear transmutation

10.2172/751584

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Citations (4)

Cool, High-Density Regime for Poloidal Divertors

Physical Review Letters (1982)

M. Petravić D.E. Post D. Heifetz J. Schmidt

Calculations have been performed which demonstrate the possibility of operating poloidal divertors at high densities and low temperatures. Ionization of recycling neutral gas near the divertor neutralizer plate amplifies the input particle flux thereby raising the plasma density and lowering the plasma temperature. Low-temperature, high-density operation should reduce the erosion rate of the divertor walls and plate, and ease the pumping requirements in future large tokamaks.

10.1103/physrevlett.48.326

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Citations (113)

The design of the Tokamak Physics Experiment (TPX)

Journal of Fusion Energy (1993)

J. Schmidt K.I. Thomassen R.J. Goldston G.H. Neilson W. M. Nevins

Fusion power

Bootstrap current

Limiter

10.1007/bf01079667

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Citations (19)

NCSX Construction Progress and Research Plans

21st IEEE/NPS Symposium on Fusion Engineering SOFE 05 (2005)

G.H. Neilson P. Heitzenroeder J. F. Lyon Bradley J. Nelson W. Reiersen

Stellarators use 3D plasma and magnetic field shaping to produce a steady-state disruption-free magnetic confinement configuration. Compact stellarators have additional attractive properties-quasi-symmetric magnetic fields and low aspect ratio. The National Compact Stellarator Experiment (NCSX) is being constructed at the Princeton Plasma Physics Laboratory (PPPL) in partnership with the Oak Ridge National Laboratory (ORNL) to test the physics of a high-beta compact stellarator with a low-ripple, tokamak-like magnetic configuration. The engineering challenges of NCSX stem from its complex geometry requirements. These issues are addressed in the construction project through manufacturing R&D and system engineering. As a result, the fabrication of the coil winding forms and vacuum vessel are proceeding in industry without significant technical issues, and preparations for winding the coils at PPPL are in place. Design integration, analysis, and dimensional control are functions provided by system engineering to ensure that the finished product will satisfy the physics requirements, especially accurate realization of the specified coil geometries. After completion of construction in 2009, a research program to test the expected physics benefits will start

Plasma confinement

10.1109/fusion.2005.252851

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Determination of the Electron Thermal Conductivity across Magnetic Surfaces in the FM-1 Spherator

Physical Review Letters (1974)

S. Ejima M. Okabayashi J. Schmidt

A new approach was taken to measure the electron thermal conductivity across magnetic surfaces by utilizing localized upper hybrid resonance heating. The electron thermal conductivity coefficient measured in the FM-1 spherator was increased with an increase of electron temperature for ${T}_{e}>1$ eV. The dependence is similar to that of the particle diffusion coefficient. The absolute value was 10-20 times smaller than the Bohm coefficient.

10.1103/physrevlett.32.872

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Citations (13)

Development of Energy Models with Limited Data to Optimize Use and Benefits of Renewable Energy Resources in Isolated Food-Energy-Water Systems: A Remote Alaska Community Example

AGU Fall Meeting Abstracts (2019)

Justus Karenzi Richard Wies Daniel J. Sambor Erin Whitney Daisy Huang

Food energy

Energy development

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FED-INTOR activity

Weston M. Stacey Abdou D.B. Montgomery J.M. Rawls J. Schmidt

A set of critical technical issues affecting near-term tokamak reactors has been addressed by a broad cross section of the USA fusion community. The results of this work have guided the evolution of an improved concept for a tokamak experimental reactor.

Fusion power

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U. S. Fusion Energy Future

J. Schmidt Dan Jassby S. Larson Maria Pueyo P. H. Rutherford

Fusion implementation scenarios for the US have been developed. The dependence of these scenarios on both the fusion development and implementation paths has been assessed. A range of implementation paths has been studied. The deployment of CANDU fission reactors in Canada and the deployment of fission reactors in France have been assessed as possible models for US fusion deployment. The waste production and resource (including tritium) needs have been assessed. The conclusion that can be drawn from these studies is that it is challenging to make a significant impact on energy production during this century. However, the rapid deployment of fission reactors in Canada and France support fusion implementation scenarios for the US with significant power production during this century. If the country can meet the schedule requirements then the resource needs and waste production are found to be manageable problems.

Fusion power

10.2172/765153

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Citations (1)