THERMAL FIELDS OF ROD-TYPE FUEL-ELEMENTS SITUATED IN REGULAR LATTICES STREAMLINED BY A HEAT CARRIER

被引：0

作者：

USHAKOV, PA ^{[1
]}

ZHUKOV, AV ^{[1
]}

MATYUKHIN, NM ^{[1
]}

机构：

[1] MOSCOW ENGN PHYS INST,MOSCOW,USSR

来源：

HIGH TEMPERATURE | 1976年 / 14卷 / 03期

关键词：

D O I：

暂无

中图分类号：

O59 [应用物理学];

学科分类号：

摘要：

The mean heat exchange and temperature nonuniformity on the surface of a rod-type fuel element is solved and calculated. The results can be applied to rod-type fuel elements of arbitrary composition in the reliability analysis during cooling when reactor is shut-down.

引用

页码：482 / 488

页数：7

共 14 条

[1] EFFICIENCY OF RIBBING OF ROD-TYPE FUEL-ELEMENTS
DOSTOV, AI
ZORIKOEV, GA
SIDOROV, VS
HIGH TEMPERATURE, 1976, 14 (03) : 488 - 493
[2] HYDRAULIC RESISTANCE OF SPACER ELEMENTS MADE FROM SLEEVES FOR BUNDLES OF ROD-TYPE FUEL-ELEMENTS
KOROTAEV, OI
PUCHKOV, PI
FEDOROVICH, ED
THERMAL ENGINEERING, 1980, 27 (12) : 683 - 686
[3] CALCULATION OF HEAT-EXCHANGE FOR ROD-LIKE FLOW AND HYDRODYNAMICS FOR LAMINAR-FLOW OF A COOLANT IN REGULAR LATTICES OF FUEL-ELEMENTS
SUBBOTIN, VI
USHAKOV, PA
ZHUKOV, AV
MATYUKHI.NM
ATOMNAYA ENERGIYA, 1972, 33 (04): : 840 - &
[4] ELASTIC ANALYSIS OF THERMAL-GRADIENT BOWING IN ROD-TYPE FUEL ELEMENTS SUBJECTED TO AXIAL THRUST
NEWMAN, JB
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1967, 10 (02): : 663 - &
[5] PARALLEL-DIFFUSION LENGTH OF THERMAL-NEUTRONS IN ROD-TYPE LATTICES
AHMED, T
KHAN, AM
SIDDIQUI, SAMM
LETTERE AL NUOVO CIMENTO, 1982, 33 (14): : 475 - 479
[6] HEAT-TRANSFER TO LIQUID-METALS IN REGULAR ARRAYS OF FUEL-ELEMENTS
USHAKOV, PA
ZHUKOV, AV
MATYUKHIN, NM
HIGH TEMPERATURE, 1977, 15 (05) : 868 - 873
[7] INELASTIC ANALYSIS OF BOWING IN ROD-TYPE FUEL ELEMENTS SUBJECTED TO AXIAL THRUST
NEWMAN, JB
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1968, 11 (01): : 134 - &
[8] ANALYSIS OF TRANSIENT CAPABILITY OF ROD-TYPE FUEL ELEMENTS (LWBR DEVELOPMENT PROGRAM)
CAMPBELL, WR
GOLDBERG, I
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1970, 13 (01): : 350 - &
[9] UNSTEADY THERMAL-STRESSES IN FUEL-ELEMENTS UNDER HEAT GENERATION
TAKEUTI, Y
NODA, N
NUCLEAR ENGINEERING AND DESIGN, 1974, 30 (03) : 328 - 338
[10] THERMAL-NEUTRON SPECTRUM IN A REACTOR CORE WITH MTR TYPE FUEL-ELEMENTS
ANUSCHEWSKI, P
TAHA, M
MERTINS, H
KRULL, W
LAHANN, HJ
ATOMKERNENERGIE, 1972, 19 (02): : 171 - +

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