IMPROVEMENT OF PHYSICAL CHARACTERISTICS OF FAST PLUTONIUM REACTORS BY USING U-233 AND THORIUM

被引：0

作者：

LEIPUNSK.AI

BOBROV, SB

TROYANOV, MF

TOCHENYI, LV

YUROVA, LN

SHMELEV, AN

MUROGOV, VM

机构：

来源：

SOVIET ATOMIC ENERGY-USSR | 1971年 / 30卷 / 06期

关键词：

D O I：

10.1007/BF01172067

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：

引用

页码：609 / &

共 50 条

[1] INTEGRAL TESTING OF THORIUM AND U-233 DATA FOR THERMAL-REACTORS
HARDY, J
ULLO, JJ
STEEN, NM
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1978, 28 (JUN): : 714 - 715
[2] INTEGRAL TESTING OF THORIUM AND U-233 DATA FOR THERMAL-REACTORS
HARDY, J
ULLO, JJ
STEEN, NM
PROGRESS IN NUCLEAR ENERGY, 1979, 4 (02) : 119 - 160
[3] REVIEW OF FAST INTEGRAL DATA RELATED TO U-233 AND THORIUM
BECK, CL
LINEBERRY, MJ
SCHAEFER, RW
CARPENTER, SG
WADE, DC
DUCAT, GA
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1978, 28 (JUN): : 715 - 717
[4] REACTIVITY EFFECTS OF PROTACTINIUM-233 BUILDUP IN U-233 FAST BREEDER REACTORS
GOLDMAN, AJ
NUCLEAR SCIENCE AND ENGINEERING, 1961, 10 (01) : 91 - 92
[5] U-233 CONCENTRATION IN THORIUM-BEARING ORES
GARZONRUIPEREZ, L
ANALES DE FISICA, 1975, 71 (03): : 244 - 248
[6] RELATIVE OCCUPATIONAL RISKS OF PLUTONIUM AND U-233 FUELS
LANGER, S
LAWROSKI, H
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1977, 27 (NOV): : 130 - 131
[7] U-233 BREEDING AND NEUTRON MULTIPLYING BLANKETS FOR FUSION REACTORS
COOK, AG
MANISCALCO, JA
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1976, 23 (JUN18): : 25 - 26
[8] BREEDING RATIO IN U-233 AND PU-239 FUELED REACTORS
LEVINE, MM
NUCLEAR SCIENCE AND ENGINEERING, 1960, 7 (06) : 545 - 551
[9] NEUTRON PHYSICS ANALYSIS OF THERMIONIC REACTORS WITH U-233 AS FUEL AND BERYLLIUM AS MODERATOR
SAHIN, S
ANNALS OF NUCLEAR ENERGY, 1976, 3 (9-10) : 447 - 450
[10] SOME ASPECTS OF U-233 ENRICHED FUEL FOR LIGHT WATER-REACTORS
RONEN, Y
COJOCARU, M
ANNALS OF NUCLEAR ENERGY, 1978, 5 (05) : 177 - 178

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