Breeder-in-tube design for a helium-cooled Li sub 2 O tokamak blanket
Abstract
Of the solid breeder designs considered in the Blanket Comparison and Selection Study (BCSS), the lithium oxide breeder with helium coolant and ferritic steel (HT-9) structural material received the highest overall ranking for both tokamak and tandem mirror systems in terms of engineering, economics, safety, and R D requirements. The BCSS blanket surrounding the fusion plasma consists of a number of thin breeder plates externally cooled by flowing helium and internally purged of tritium by a separate helium stream. A detailed review of this design indicated that significant improvements would be realized in the areas of tritium breeding, blanket thickness, blanket energy multiplication, power-conversion efficiency, breeder temperature window, and geometrical integrity of the coolant and purge paths by using a neutron multiplier (beryllium), a higher temperature structural material (vanadium-based alloy), and a tube geometry. The neutronics, thermal-hydraulics, tritium recovery, and structural performance characteristics of this innovative solid breeder design are discussed in this paper. 2 refs., 1 tab.
- Authors:
- Publication Date:
- OSTI Identifier:
- 6860697
- Report Number(s):
- CONF-860610-Summs.
Journal ID: ISSN 0003-018X; CODEN: TANSA; TRN: 90-022119
- Resource Type:
- Conference
- Journal Name:
- Transactions of the American Nuclear Society; (USA)
- Additional Journal Information:
- Journal Volume: 52; Conference: American Nuclear Society annual meeting, Reno, NV (USA), 15-20 Jun 1986; Journal ID: ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; BREEDING BLANKETS; DESIGN; TOKAMAK TYPE REACTORS; BERYLLIUM; BREEDING RATIO; CHROMIUM ALLOYS; HELIUM; HYDRAULICS; LITHIUM OXIDES; MULTIPLICATION FACTORS; NEUTRON TRANSPORT; PERFORMANCE; THERMONUCLEAR REACTOR COOLING SYSTEMS; TITANIUM ALLOYS; TRITIUM; TRITIUM RECOVERY; TUBES; VANADIUM BASE ALLOYS; WALL LOADING; ALKALI METAL COMPOUNDS; ALKALINE EARTH METALS; ALLOYS; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CHALCOGENIDES; CONVERSION RATIO; COOLING SYSTEMS; ELEMENTS; ENERGY SYSTEMS; FLUID MECHANICS; FLUIDS; GASES; HYDROGEN ISOTOPES; ISOTOPES; LIGHT NUCLEI; LITHIUM COMPOUNDS; MECHANICS; METALS; NEUTRAL-PARTICLE TRANSPORT; NONMETALS; NUCLEI; ODD-EVEN NUCLEI; OXIDES; OXYGEN COMPOUNDS; POWER DENSITY; RADIATION TRANSPORT; RADIOISOTOPES; RARE GASES; REACTOR COMPONENTS; RECOVERY; THERMONUCLEAR REACTORS; VANADIUM ALLOYS; YEARS LIVING RADIOISOTOPES; 700201* - Fusion Power Plant Technology- Blanket Engineering
Citation Formats
Billone, M C, Jung, J, Liu, Y Y, and Smith, D L. Breeder-in-tube design for a helium-cooled Li sub 2 O tokamak blanket. United States: N. p., 1986.
Web.
Billone, M C, Jung, J, Liu, Y Y, & Smith, D L. Breeder-in-tube design for a helium-cooled Li sub 2 O tokamak blanket. United States.
Billone, M C, Jung, J, Liu, Y Y, and Smith, D L. 1986.
"Breeder-in-tube design for a helium-cooled Li sub 2 O tokamak blanket". United States.
@article{osti_6860697,
title = {Breeder-in-tube design for a helium-cooled Li sub 2 O tokamak blanket},
author = {Billone, M C and Jung, J and Liu, Y Y and Smith, D L},
abstractNote = {Of the solid breeder designs considered in the Blanket Comparison and Selection Study (BCSS), the lithium oxide breeder with helium coolant and ferritic steel (HT-9) structural material received the highest overall ranking for both tokamak and tandem mirror systems in terms of engineering, economics, safety, and R D requirements. The BCSS blanket surrounding the fusion plasma consists of a number of thin breeder plates externally cooled by flowing helium and internally purged of tritium by a separate helium stream. A detailed review of this design indicated that significant improvements would be realized in the areas of tritium breeding, blanket thickness, blanket energy multiplication, power-conversion efficiency, breeder temperature window, and geometrical integrity of the coolant and purge paths by using a neutron multiplier (beryllium), a higher temperature structural material (vanadium-based alloy), and a tube geometry. The neutronics, thermal-hydraulics, tritium recovery, and structural performance characteristics of this innovative solid breeder design are discussed in this paper. 2 refs., 1 tab.},
doi = {},
url = {https://www.osti.gov/biblio/6860697},
journal = {Transactions of the American Nuclear Society; (USA)},
issn = {0003-018X},
number = ,
volume = 52,
place = {United States},
year = {Wed Jan 01 00:00:00 EST 1986},
month = {Wed Jan 01 00:00:00 EST 1986}
}