CANDU-PHW PROGRAM/E

被引：0

作者：

GRAY, JL ^{[1
]}

机构：

[1] ATOM ENERGY CANADA LTD,OTTAWA,ONTARIO,CANADA

来源：

NUCLEAR ENGINEERING INTERNATIONAL | 1974年 / 19卷 / 217期

关键词：

D O I：

暂无

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：476 / 477

页数：2

共 50 条

[11] FACTORS AFFECTING CREEP SAG OF FUEL CHANNELS IN CANDU-PHW REACTORS
CAUSEY, AR
NORSWORTHY, AG
SCHULTE, CW
CANADIAN METALLURGICAL QUARTERLY, 1985, 24 (03) : 207 - 214
[12] SEISMIC DESIGN MARGINS FOR CANDU-PHW NUCLEAR-POWER PLANTS
DUFF, CG
MECHANICAL ENGINEERING, 1978, 100 (11) : 116 - 117
[13] FACTORS AFFECTING CREEP SAG OF FUEL CHANNELS IN CANDU-PHW REACTORS.
Causey, A.R.
Norsworthy, A.G.
Schulte, C.W.
1985, (24)
[14] COMMISSIONING AND OPERATING EXPERIENCE WITH CANDU-PHW COMMERCIAL NUCLEAR-ELECTRIC STATIONS
WOODHEAD, LW
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1978, 29 (SEP): : 184 - 190
[15] CHANNEL POWER PEAKING IN LOW-ENRICHED URANIUM (LEU) CANDU-PHW REACTORS
LAU, JHK
BONALUMI, RA
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1979, 33 (NOV): : 402 - 403
[16] RELIABILITY STUDY OF REACTOR CONTROL-SYSTEM FOR A CANDU-PHW NUCLEAR UNIT
BASU, S
KEE, FJ
IEEE TRANSACTIONS ON POWER APPARATUS AND SYSTEMS, 1978, 97 (02): : 334 - 334
[17] THE INFLUENCE OF AXIAL END LOADS ON CRITICAL CRACK LENGTH BEHAVIOR OF CANDU-PHW PRESSURE TUBING
WILKINS, BJS
REICH, AR
BARRIE, JN
INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, 1982, 10 (01) : 69 - 75
[18] A RESOURCE UTILIZATION AND ECONOMIC-ASSESSMENT OF ALTERNATIVE FUEL-CYCLES FOR CANDU-PHW REACTORS
ARCHINOFF, GH
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1982, 40 : 226 - 230
[19] PERFORMANCE REVIEW OF CANDU-PHW NUCLEAR-ELECTRIC UNITS AND BRUCE HEAVY-WATER PLANT
WOODHEAD, LW
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1976, 23 (JUN18): : 418 - 419
[20] CHEMICAL BEHAVIOR OF MORPHOLINE IN THE STEAM-WATER CYCLE OF A CANDU-PHW NUCLEAR-POWER-PLANT
GILBERT, R
LAMARRE, C
DUNDAR, Y
10TH ANNUAL CONFERENCE 1989 - CANADIAN NUCLEAR SOCIETY, PROCEEDINGS VOL 3, 1989, : H1 - H9

← 1 2 3 4 5 →