SUBCOOLED FLOW BOILING CRITICAL HEAT-FLUX (CHF) AND ITS APPLICATION TO FUSION ENERGY COMPONENTS .2. A REVIEW OF MICROCONVECTIVE, EXPERIMENTAL, AND CORRELATIONAL ASPECTS

被引：31

作者：

BOYD, RD

机构：

[1] Sandia Natl Lab, Albuquerque, NM,, USA, Sandia Natl Lab, Albuquerque, NM, USA

来源：

FUSION TECHNOLOGY | 1985年 / 7卷 / 01期

关键词：

D O I：

10.13182/FST85-A24516

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：

147

引用

页码：31 / 52

页数：22

共 145 条

[1] FLUID TO FLUID MODELING OF CRITICAL HEAT-FLUX - COMPENSATED DISTORTION MODEL [J].

AHMAD, SY .

INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, 1973, 16 (03) :641-662

[2]

Andreyev P. A., 1980, Heat Transfer - Soviet Research, V12, P64

[3]

[Anonymous], 1978, MEASUREMENT 2 PHASE

[4] INSTABILITIES IN PARALLEL CHANNEL OF FORCED-CONVECTION BOILING UPFLOW SYSTEM .3. SYSTEM WITH DIFFERENT FLOW CONDITIONS BETWEEN 2 CHANNELS [J].

ARITOMI, M ;

AOKI, S ;

INOUE, A .

JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 1979, 16 (05) :343-355

[5] INTENSE NEUTRON SOURCE TARGET TEST FACILITY - 200 KV, 200 MA DC,DEUTERIUM ION ACCELERATOR [J].

BACON, FM ;

RIEDEL, AA .

IEEE TRANSACTIONS ON NUCLEAR SCIENCE, 1979, 26 (01) :1505-1508

[6]

BARANENKO VI, 1973, ZH APPL MECH TECH PH, V1, P144

[7]

BARANENKO VI, 1974, 5TH P INT C HEAT TRA, V1, P50

[8]

BARANENKO VI, 1978, 6TH P INT C HEAT TRA, V1, P305

[9] A SIMPLE 2-PHASE FRICTIONAL PRESSURE-DROP CALCULATION METHOD [J].

BEATTIE, DRH ;

WHALLEY, PB .

INTERNATIONAL JOURNAL OF MULTIPHASE FLOW, 1982, 8 (01) :83-87

[10] A GENERALIZATION OF THE SYSTEM MEAN VOID FRACTION MODEL FOR TRANSIENT 2-PHASE EVAPORATING FLOWS [J].

BECK, BT ;

WEDEKIND, GL .

JOURNAL OF HEAT TRANSFER-TRANSACTIONS OF THE ASME, 1981, 103 (01) :81-85

← 1 2 3 4 5 6 7 8 9 10 →