Published July 1978 | Version v1
Report

New initiatives in laser driven fusion--fision

  • 1. Lawrence Livermore Lab., CA

Description

It was demonstrated that fusion-fission hybrids exhibit the best energy multiplication and fissile fuel production performance when the region closest to the fusion source is a uranium fast-fission blanket, and the potential of this type of blanket was explored with two different after-blanket options: A 233U-producing thorium after-blanket, and a power-producing thermal lattice. The neutronic analysis of the thorium after-blanket option leads one to conclude that one can design a laser fusion driven hybrid which multiplies the fusion neutron energy by a factor of five and produces enough 233U to fuel more than ten thermal burner reactors of equivalent thermal power. With capital costs in the neighborhood of three times an LWR, the cost of electricity in the combined hybrid-burner reactor scenario can be expected to increase less than 30% over present prices

Additional details

Publishing Information

Imprint Title
Proceedings of the second fusion--fission energy systems review meeting. Volume I
Journal Page Range
p. 277-296.
Report number
CONF-771155--P1

Conference

Title
2. DMFE hybrid reactor meeting.
Dates
2 - 3 Nov 1977.
Place
Washington, DC, USA.

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
10443041
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BREEDING BLANKETS; FUEL CYCLE; HYBRID REACTORS; LASER IMPLOSIONS; SPECIFICATIONS; URANIUM 233
Descriptors DEC
ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; EVEN-ODD NUCLEI; HEAVY NUCLEI; IMPLOSIONS; ISOTOPES; NUCLEI; RADIOISOTOPES; REACTOR COMPONENTS; URANIUM ISOTOPES; YEARS LIVING RADIOISOTOPES