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Title: Counterstreaming-ion-tokamak fissile breeder

Abstract

Tokamak plasmas fueled and heated by energetic neutral-atom beams are characterized by total ion energy greatly exceeding the electron energy. For smaller devices the largest fusion reactivity of energetic-ion plasmas is obtained when oppositely injected D/sup 0/ and T/sup 0/ beams sustain counterstreaming velocity distributions of deuterons and tritons. This scoping study investigates the net fissile and power productions of a tokamak fusion-fission reactor with a counterstreaming-ion fusion driver and a fertile blanket optimized for fissile breeding. The fusion driver has parameters R/sub o/ = 4.7 m, a = 1.0 m, B/sub t/ = 5.6 T, W/sub b/ = 100 keV (D/sup 0/), n tau/sub E/ = 1.4 x 10/sup 13/ cm/sup -3/s, Q = 1.5, 14-MeV neutron production = 175 MW. The blanket contains a fast-fission zone of natural U plus Mo (7 percent), followed by a Li-bearing zone for T breeding. The reactor produces a net power of 480 MWe and supplies sufficient Pu to support a system of LWR's producing 3800 MWe, with an estimated electrical energy cost for the entire system of 27 mills/kWh.

Authors:
;
Publication Date:
Research Org.:
Princeton Univ., N.J. (USA). Plasma Physics Lab.
OSTI Identifier:
7333291
Report Number(s):
MATT-1255; CONF-760733-3
TRN: 77-000968
DOE Contract Number:  
E(11-1)-3073
Resource Type:
Conference
Resource Relation:
Conference: Joint US-USSR symposium on fusion fission reactor, Livermore, CA, USA, 13 Jul 1976
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; HYBRID REACTORS; SPECIFICATIONS; TOKAMAK TYPE REACTORS; BREEDING; BREEDING BLANKETS; COST; DEUTERONS; FISSION; NEUTRAL ATOM BEAM INJECTION; TRITONS; URANIUM 238; ACTINIDE ISOTOPES; ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; BEAM INJECTION; CHARGED PARTICLES; EVEN-EVEN NUCLEI; HEAVY NUCLEI; ISOTOPES; NUCLEAR FUEL CONVERSION; NUCLEAR REACTIONS; NUCLEI; RADIOISOTOPES; REACTOR COMPONENTS; THERMONUCLEAR REACTORS; URANIUM ISOTOPES; YEARS LIVING RADIOISOTOPES; 700200* - Fusion Energy- Fusion Power Plant Technology

Citation Formats

Jassby, D L, and Lee, J D. Counterstreaming-ion-tokamak fissile breeder. United States: N. p., 1976. Web.
Jassby, D L, & Lee, J D. Counterstreaming-ion-tokamak fissile breeder. United States.
Jassby, D L, and Lee, J D. 1976. "Counterstreaming-ion-tokamak fissile breeder". United States.
@article{osti_7333291,
title = {Counterstreaming-ion-tokamak fissile breeder},
author = {Jassby, D L and Lee, J D},
abstractNote = {Tokamak plasmas fueled and heated by energetic neutral-atom beams are characterized by total ion energy greatly exceeding the electron energy. For smaller devices the largest fusion reactivity of energetic-ion plasmas is obtained when oppositely injected D/sup 0/ and T/sup 0/ beams sustain counterstreaming velocity distributions of deuterons and tritons. This scoping study investigates the net fissile and power productions of a tokamak fusion-fission reactor with a counterstreaming-ion fusion driver and a fertile blanket optimized for fissile breeding. The fusion driver has parameters R/sub o/ = 4.7 m, a = 1.0 m, B/sub t/ = 5.6 T, W/sub b/ = 100 keV (D/sup 0/), n tau/sub E/ = 1.4 x 10/sup 13/ cm/sup -3/s, Q = 1.5, 14-MeV neutron production = 175 MW. The blanket contains a fast-fission zone of natural U plus Mo (7 percent), followed by a Li-bearing zone for T breeding. The reactor produces a net power of 480 MWe and supplies sufficient Pu to support a system of LWR's producing 3800 MWe, with an estimated electrical energy cost for the entire system of 27 mills/kWh.},
doi = {},
url = {https://www.osti.gov/biblio/7333291}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1976},
month = {8}
}

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