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Title: Counterstreaming-ion tokamak neutron source for large area surface radiation studies

Abstract

A tokamak neutron source that produces a neutron flux approximately 10$sup 13$ n/cm$sup 2$/s over a wall test-area of 30 m$sup 2$ is designed using near state-of-the-art tokamak and neutral-beam injection technologies. To maximize fusion reactivity, D and T plasma ions are grouped in two distinct quasi- thermal velocity distributions, oppositely displaced in velocity along the magnetic axis. Such counterstreaming distributions can be set up by tangential injection of all plasma ions by oppositely directed D and T neutral beams, by facilitating removal of completely decelerated ions, and by minimizing plasma recycling. Fusion energy is produced principally by head-on collisions between D and T ions in the counterstreaming distributions. For injection energies of 40- 60 keV, and typical tokamak parameters, the fusion power density can be approximately 1 W/cm$sup 3$, with Q approximately 1 attainable for T/sub e/ = 3.4 keV and electron energy confinement parameter n/sub e/tau/sub E/ approximately equal to 2 x 10$sup 12$ cm$sup -3$s. All plasma fueling is carried out by the injected beams, and when a significant fraction of the electron population is trapped, the plasma current can be maintained by the beams. (auth)

Authors:
Publication Date:
Research Org.:
Princeton Univ., N.J. (USA). Plasma Physics Lab.
OSTI Identifier:
4126967
Report Number(s):
MATT-1165; CONF-750723-19
NSA Number:
NSA-33-011720
DOE Contract Number:  
E(11-1)-3073
Resource Type:
Conference
Resource Relation:
Conference: International conference on radiation test facilities for the CTR surface and materials program, Argonne, Illinois, USA, 15 Jul 1975; Other Information: Orig. Receipt Date: 30-JUN-76
Country of Publication:
United States
Language:
English
Subject:
N70800* -Physics-Controlled Thermonuclear Research- Thermonuclear Engineering & Equipment; 700209* -Fusion Energy-Fusion Power Plant Technology- Component Development & Materials Testing; *NEUTRON SOURCES; *THERMONUCLEAR REACTOR MATERIALS- MATERIALS TESTING; *TOKAMAK DEVICES- NEUTRON SOURCES; ION BEAMS; NEUTRON FLUX; SURFACES

Citation Formats

Jassby, D. L. Counterstreaming-ion tokamak neutron source for large area surface radiation studies. United States: N. p., 1975. Web.
Jassby, D. L. Counterstreaming-ion tokamak neutron source for large area surface radiation studies. United States.
Jassby, D. L. 1975. "Counterstreaming-ion tokamak neutron source for large area surface radiation studies". United States. https://www.osti.gov/servlets/purl/4126967.
@article{osti_4126967,
title = {Counterstreaming-ion tokamak neutron source for large area surface radiation studies},
author = {Jassby, D. L.},
abstractNote = {A tokamak neutron source that produces a neutron flux approximately 10$sup 13$ n/cm$sup 2$/s over a wall test-area of 30 m$sup 2$ is designed using near state-of-the-art tokamak and neutral-beam injection technologies. To maximize fusion reactivity, D and T plasma ions are grouped in two distinct quasi- thermal velocity distributions, oppositely displaced in velocity along the magnetic axis. Such counterstreaming distributions can be set up by tangential injection of all plasma ions by oppositely directed D and T neutral beams, by facilitating removal of completely decelerated ions, and by minimizing plasma recycling. Fusion energy is produced principally by head-on collisions between D and T ions in the counterstreaming distributions. For injection energies of 40- 60 keV, and typical tokamak parameters, the fusion power density can be approximately 1 W/cm$sup 3$, with Q approximately 1 attainable for T/sub e/ = 3.4 keV and electron energy confinement parameter n/sub e/tau/sub E/ approximately equal to 2 x 10$sup 12$ cm$sup -3$s. All plasma fueling is carried out by the injected beams, and when a significant fraction of the electron population is trapped, the plasma current can be maintained by the beams. (auth)},
doi = {},
url = {https://www.osti.gov/biblio/4126967}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1975},
month = {11}
}

Conference:
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