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QNPP STEAM GENERATOR TUBE RUPTURE ACCIDENT ANALYSIS
PU SHENGDI;LI JIGEN China Institute of Atomic Energy, P. O. Box 275(59), Beijing, 102413
1993, 27(4): 289-289. DOI: 10.7538/yzk.1993.27.04.0289
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ATWS ANALYSIS AND ITS MANAGEMENT FOR QINSHAN NUCLEAR POWER PLANT
SUN LIYA;PU JILONG;LIN CHENGGE China Institute of Atomic Energy, P. O. Box 275 (59), Beijing, 102413
1993, 27(4): 295-295. DOI: 10.7538/yzk.1993.27.04.0295
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MAIN STEAM LINE BREAK (MSLB) ACCIDENT ANALYSIS FOR QINSHAN NUCLEAR POWER PLANT (QNPP) WITH RELAP5/MOD2
SUN JILIANG;YU ERJUN China Institute of Atomic Energy, P. O. Box 275, Beijing, 102413
1993, 27(4): 304-304. DOI: 10.7538/yzk.1993.27.04.0304
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DNBR CALCULATION IN CORE DURING COOLANT PUMP ROTOR SEIZURE ACCIDENT FOR QINSHAN NUCLEAR POWER PLANE
HAO LAOMI China Institute of Atomic Energy, P. O. Box 275, Beijing, 102413
1993, 27(4): 309-309. DOI: 10.7538/yzk.1993.27.04.0309
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IHERMAL-HYDRAULIC CALCULATION AND ANALYSIS FOR QNPP CONTAINMENT
XIE HUI;ZHOU JIE;HE YLINGCHAO China Institute of Atomit Energy, P. O. Box 275, Beijing, 102413
1993, 27(4): 314-314. DOI: 10.7538/yzk.1993.27.04.0314
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AUDIT CALCULATIONS OF CONTROL ROD EJECTION ACCIDENTS FOR QINSHANG NUCLEAR POWER STATION
YANG SHUNHAI China Institute of Atomic Energy, P. O. Box 275(45), Beijing, 102413
1993, 27(4): 320-320. DOI: 10.7538/yzk.1993.27.04.0320
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HUMAN RELIABILITY ANALYSIS FOR GUANGDONG NUCLEAR POWER STATION
Li Xiaohua China Institute of Atomic Energy, P. O. Box 275(45), Beijing, 102413
1993, 27(4): 324-324. DOI: 10.7538/yzk.1993.27.04.0324
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A SIMPLIFIED APPROACH FOR SOURCE TERM CALCULATION
HU ZHIYI;ZHANG NING;XU HANMING China Institute of Atomic Energy, P. O. Box 275(45), Beijing, 102413
1993, 27(4): 329-329. DOI: 10.7538/yzk.1993.27.04.0329
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RESEARCH ON LEAKAGE DETECTION OF NUCLEAR POWER STATION PRIMARY LOOP
CAO SHENGQUAN;YANG JICAI;LI JIANJUN;DONG ZHIJUAN;REN JUYAN;ZHANG PINYUAN China Institute of Atomic Energy, P. O. Box 275, Beijing, 102413
1993, 27(4): 336-336. DOI: 10.7538/yzk.1993.27.04.0336
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ASSESSMENT OF TWO-PHASE CRITICAL FLOW MODELS OF RELAN5/MOD2 AND CATHARE CODE
HAO LAOMI;ZHU ZHANCHUAN China Institute of Atomic Energy, P. O. Box275, Beijing, 102413
1993, 27(4): 340-340. DOI: 10.7538/yzk.1993.27.04.0340
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THE REFLOODING HEAT TRANSFER EXPERIMENM IN ROD BOUNDLE
SHI MINGZHE;XU GUOHUA China Institute of Atomic Energy, P. O. Box 275, Beijing, 102413
1993, 27(4): 348-348. DOI: 10.7538/yzk.1993.27.04.0348
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FAMSAP: A CODE TO ANALYZE THE DYNAMIC RESPONSE OF PWR FUEL ASSEMBLIES IN LOCA AND SEISMIC CONDITIONS
ZHANG CHONGZHU;ZHANG ZHONGYUE China Institute of Atomic Energy, P. O. Box 275--64, Beijing, 102413
1993, 27(4): 353-353. DOI: 10.7538/yzk.1993.27.04.0353
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A MODIFIED METHOD FOR UNCERTAINTY ANALYSIS
SUN SONGQIN;ZHANG ZHONGYUE China Institute of Atomic Energy, P. O. Box 275, Beijing, 102413
1993, 27(4): 359-359. DOI: 10.7538/yzk.1993.27.04.0359
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STRESS CORROSION CRACKING OF STEAM GENERATOR TUBE AND PRIMARY PIPE IN PWR TYPE NUCLEAR POWER PLANTS
ZHANG WEIGUO;GAO FENGQIN;ZHOU HONGYI China Institute of Atomic Energy, P. O. Box 275, Beijing, 102413
1993, 27(4): 367-367. DOI: 10.7538/yzk.1993.27.04.0367
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STUDY OF FUEL CLADDING-STEAM REACTION UNDER A LOSS OF COOLANT-ACCIDENT (LOCA)
MA SHUCHUN;SUN YUANZHENG;CHEN WANGCHUN;BI ANTAI China Institute of Atomic Energy, P. O. Box 275, Beijing, 102413
1993, 27(4): 376-376. DOI: 10.7538/yzk.1993.27.04.0376
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