A KRF LASER DRIVEN INERTIAL FUSION-REACTOR SOMBRERO

被引:56
|
作者
SVIATOSLAVSKY, IN
SAWAN, ME
PETERSON, RR
KULCINSKI, GL
MACFARLANE, JJ
WITTENBERG, LJ
KHATER, HY
MOGAHED, EA
RUTLEDGE, SC
GHOSE, S
BOURQUE, R
机构
[1] BECHTEL GRP INC,SAN FRANCISCO,CA
[2] GEN ATOM,SAN DIEGO,CA
来源
FUSION TECHNOLOGY | 1992年 / 21卷 / 03期
关键词
D O I
10.13182/FST92-A29928
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The SOMBRERO inertial fusion reactor conceptual design study is of a 1000 MWe KrF laser driven near symmetric illumination system which utilizes a Li2O solid breeder moving bed in a blanket made entirely of low activation carbon/carbon composite material. The Li2O particles flow through the various parts of the blanket under gravity, then are transported through an intermediate heat exchanger and around the loop in a fluidized state by helium gas at 0.2 MPa. Liquid lead is used in the intermediate loop, going to a steam generator and a double reheat steam power cycle. There are 60 beams in the near symmetric illumination configuration. The laser energy is 3.4 MJ, the target gain 118 and the rep-rate 6.7 Hz. At the midplane, the blanket thickness is 1 m giving a tritium breeding ratio of 1.25 and an overall energy multiplication of 1.08. The first wall is at 6.5 m radius and is protected from x-rays and ions by 0.5 torr of Xe gas. Grazing incidence metallic mirrors are located at a distance of 30 m and dielectric final focusing mirrors at 50 m from the target. Source neutrons are directed into neutron traps located in line with the grazing incidence mirrors. The final focusing mirrors which are out of line of sight of source neutron are subjected to low energy scattered neutrons only and can survive the 30 full power year reactor lifetime. The Li2O particles enter the chamber at 550-degrees-C and exit at an average temperature of 740-degrees-C, giving a power cycle efficiency of 47%. The gross power output is 1360 MW and for a 7% laser efficiency, the driver power is 325 MWe, with the remaining 35 MWe used for auxiliary equipment. The chamber and shield qualify for near surface burial as Class A waste while the Li2O breeder, as Class C waste.
引用
收藏
页码:1470 / 1474
页数:5
相关论文
共 50 条
  • [21] BLANKET OPTIMIZATION STUDIES FOR THE HYLIFE INERTIAL CONFINEMENT FUSION-REACTOR
    MEIER, WR
    MORSE, EC
    FUSION TECHNOLOGY, 1985, 8 (03): : 2681 - 2695
  • [22] DESIGN OF LASER FUSION-REACTOR DRIVEN BY LASER-DIODE-PUMPED SOLID-STATE LASER
    KITAGAWA, Y
    MIMA, K
    TAKABE, H
    YAMANAKA, M
    NAITO, K
    HASHIMOTO, T
    NISHIHARA, K
    MURAKAMI, M
    NAKAI, S
    FUSION TECHNOLOGY, 1992, 21 (03): : 1460 - 1464
  • [23] TERRESTRIAL AND EXTRATERRESTRIAL SUPERRESONATORS AS DRIVERS FOR AN INERTIAL CONFINEMENT FUSION-REACTOR
    SEIFRITZ, W
    VATH, W
    FUSION TECHNOLOGY, 1992, 21 (01): : 5 - 11
  • [24] PELLET DELIVERY FOR THE CONCEPTUAL INERTIAL CONFINEMENT FUSION-REACTOR HIBALL
    KREUTZ, R
    FUSION TECHNOLOGY, 1985, 8 (03): : 2708 - 2720
  • [25] ANALYSIS AND EXPERIMENTS IN SUPPORT OF INERTIAL CONFINEMENT FUSION-REACTOR CONCEPTS
    MOSES, GA
    PETERSON, RR
    MACFARLANE, JJ
    PHYSICS OF FLUIDS B-PLASMA PHYSICS, 1991, 3 (08): : 2324 - 2330
  • [26] FINAL DESIGN CHARACTERISTICS OF THE CASCADE INERTIAL CONFINEMENT FUSION-REACTOR
    PITTS, JH
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1985, 49 (JUN): : 116 - 117
  • [27] HEAT-TRANSFER IN INERTIAL CONFINEMENT FUSION-REACTOR SYSTEMS
    HOVINGH, J
    NUCLEAR ENGINEERING AND DESIGN, 1982, 68 (03) : 283 - 291
  • [28] DEVELOPMENT OF LOW TRITIUM TARGETS FOR INERTIAL FUSION-REACTOR SYSTEMS
    TAHIR, NA
    HOFFMANN, DHH
    LASER INTERACTION WITH MATTER, 1995, (140): : 423 - 426
  • [29] PARAMETERS OF THE FOCUSING OPTICS OF A LASER FUSION-REACTOR
    BASOV, NG
    BELOUSOV, NI
    VERGUNOVA, GA
    GRISHUNIN, PA
    DANILOV, AE
    LEBO, IG
    ROZANOV, VB
    SKLIZKOV, GV
    SUBBOTIN, VI
    FEDOTOV, SI
    KHARITONOV, VV
    KVANTOVAYA ELEKTRONIKA, 1985, 12 (03): : 584 - 593
  • [30] SAFETY ASPECTS AND ENVIRONMENTAL-IMPACT OF AN INERTIAL CONFINEMENT FUSION-REACTOR
    KESSLER, G
    BAYER, A
    NUCLEAR ENGINEERING AND DESIGN, 1987, 100 (03) : 475 - 487