Nucleonic performance aspects of thorium fusion-fission hybrid blanket designs
- Authors:
- Publication Date:
- Research Org.:
- General Atomic Co., San Diego, CA
- OSTI Identifier:
- 5271539
- Report Number(s):
- CONF-791103-
Journal ID: CODEN: TANSA; TRN: 80-013227
- Resource Type:
- Conference
- Journal Name:
- Trans. Am. Nucl. Soc.; (United States)
- Additional Journal Information:
- Journal Volume: 33; Conference: American Nuclear Society meeting, San Francisco, CA, USA, 12 Nov 1979
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; BREEDING BLANKETS; DESIGN; HYBRID REACTORS; HYBRID SYSTEMS; NEUTRON TRANSPORT; THORIUM CARBIDES; THORIUM CYCLE; ACTINIDE COMPOUNDS; CARBIDES; CARBON COMPOUNDS; FUEL CYCLE; NEUTRAL-PARTICLE TRANSPORT; RADIATION TRANSPORT; REACTOR COMPONENTS; THORIUM COMPOUNDS; 700201* - Fusion Power Plant Technology- Blanket Engineering
Citation Formats
Cheng, E T. Nucleonic performance aspects of thorium fusion-fission hybrid blanket designs. United States: N. p., 1979.
Web.
Cheng, E T. Nucleonic performance aspects of thorium fusion-fission hybrid blanket designs. United States.
Cheng, E T. 1979.
"Nucleonic performance aspects of thorium fusion-fission hybrid blanket designs". United States.
@article{osti_5271539,
title = {Nucleonic performance aspects of thorium fusion-fission hybrid blanket designs},
author = {Cheng, E T},
abstractNote = {},
doi = {},
url = {https://www.osti.gov/biblio/5271539},
journal = {Trans. Am. Nucl. Soc.; (United States)},
number = ,
volume = 33,
place = {United States},
year = {Mon Jan 01 00:00:00 EST 1979},
month = {Mon Jan 01 00:00:00 EST 1979}
}
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