RELAP5/MOD3 analysis of transient steam-generator behavior during turbine trip test of a prototype fast breeder reactor MONJU

被引：0

作者：

Japan Nuclear Energy Safety Organization , Safety Analysis and Evaluation Division, Kamiya-cho MT Bldg., 4-3-20, Minato-ku, Tokyo, 105-0001, Japan ^{[1
]}

机构：

来源：

| 1600年 / 2006期

关键词：

Compendex;

D O I：

Fourteenth International Conference on Nuclear Engineering 2006, ICONE 14

中图分类号：

学科分类号：

摘要：

Breeder reactors - Hydraulics - Mass transfer - Nuclear energy - Two phase flow - Water supply

引用

共 10 条

[1] VALIDATION OF RELAP5/3D STEAM-GENERATOR ANALYSIS MODEL BY TURBINE TRIP TEST AT THE PROTOTYPE FAST BREEDER REACTOR MONJU
Shindo, Yoshihisa
Endo, Hiroshi
Ishizu, Tomoko
Haga, Kazuo
ICONE16: PROCEEDING OF THE 16TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2008, VOL 3, 2008, : 579 - 588
[2] STEADY-STATE SIMULATIONS OF A 30-TUBE ONCE-THROUGH STEAM-GENERATOR WITH THE RELAP5/MOD3 AND RELAP5/MOD2 COMPUTER CODES
HASSAN, YA
SALIM, P
NUCLEAR TECHNOLOGY, 1991, 96 (01) : 123 - 128
[3] ANALYSIS OF EXPERIMENTS FOR STEAM CONDENSATION IN THE PRESENCE OF NONCONDENSABLE GASES USING THE RELAP5 MOD3 CODE
HASSAN, YA
RAJA, LL
NUCLEAR TECHNOLOGY, 1993, 104 (01) : 76 - 88
[4] ANALYSIS OF SMALL-BREAK LOCA AT ACME TEST FACILITY USING RELAP5/MOD3
Xu Caihong
Shi Guobao
Fan Pu
PROCEEDINGS OF THE 24TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2016, VOL 3, 2016,
[5] ANALYSIS OF FLECHT-SEASET STEAM-GENERATOR TESTS WITH TRAC-PF1 AND RELAP5/MOD1
SLOVIK, G
SAHA, P
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1983, 44 : 594 - 595
[6] PEACH-BOTTOM TURBINE TRIP TEST-3 ANALYSIS WITH RELAP5 CODE
LU, MS
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1983, 45 : 449 - 450
[7] Evaluation of RELAP5/MOD3 behavior against loss of flow experimental results from two research reactor facilities
Chatzidakis, S.
Ikonomopoulos, A.
Ridikas, D.
NUCLEAR ENGINEERING AND DESIGN, 2013, 255 : 321 - 329
[8] STEADY-STATE AND TRANSIENT PREDICTION OF A 19-TUBE ONCE-THROUGH STEAM-GENERATOR USING RELAP5 MOD1
HASSAN, YA
MORGAN, CD
NUCLEAR TECHNOLOGY, 1983, 60 (01) : 143 - 150
[9] SIMULATION OF LOSS OF RHR DURING MIDLOOP OPERATIONS AND THE ROLE OF STEAM-GENERATORS IN DECAY HEAT REMOVAL USING THE RELAP5/MOD3 CODE
HASSAN, YA
RAJA, LL
NUCLEAR TECHNOLOGY, 1993, 103 (03) : 310 - 319
[10] RELAP5 MOD3 SIMULATION OF THE LOSS OF THE RESIDUAL HEAT REMOVAL SYSTEM DURING A MIDLOOP OPERATION EXPERIMENT CONDUCTED AT THE ROSA-IV LARGE-SCALE TEST FACILITY
HASSAN, YA
BANERJEE, SS
NUCLEAR TECHNOLOGY, 1994, 108 (02) : 191 - 206

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