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Development of mechanistic cladding rupture model for integrated severe accident code ISAA. Part II: DVI line small-break LOCA in CAP1400
Annals of Nuclear Energy
◽
10.1016/j.anucene.2021.108613
◽
2021
◽
Vol 164
◽
pp. 108613
Author(s):
Pengcheng Gao
◽
Bin Zhang
◽
Jishen Li
◽
Shaowei Tang
◽
Jianqiang Shan
Keyword(s):
Severe Accident
◽
Rupture Model
Download Full-text
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References
Development of mechanistic cladding rupture model for severe accident analysis and application in PHEBUS FPT3 experiment
Nuclear Engineering and Technology
◽
10.1016/j.net.2021.07.029
◽
2021
◽
Author(s):
Pengcheng Gao
◽
Bin Zhang
◽
Jishen Li
◽
Jianqiang Shan
Keyword(s):
Severe Accident
◽
Accident Analysis
◽
Rupture Model
Download Full-text
Development of mechanistic cladding rupture model for integrated severe accident code ISAA. Part I: Module verification and application in CAP1400
Annals of Nuclear Energy
◽
10.1016/j.anucene.2021.108305
◽
2021
◽
Vol 158
◽
pp. 108305
Author(s):
Pengcheng Gao
◽
Bin Zhang
◽
Jishen Li
◽
Shaowei Tang
◽
Jianqiang Shan
Keyword(s):
Severe Accident
◽
Rupture Model
Download Full-text
STATUS AND MAIN UNCERTAINTIES IN LEADING SEVERE ACCIDENT ANALYSIS CODES
Proceedings of the International Symposium
◽
10.1615/ichmt.1995.radtransfprocheatmasstransfsevnuclreactacc.490
◽
1995
◽
Author(s):
U. Brockmeier
Keyword(s):
Severe Accident
◽
Accident Analysis
Download Full-text
THE RELEASE AND TRANSPORT OF LOW VOLATILITY FISSION PRODUCTS UNDER SEVERE ACCIDENT CONDITIONS
Proceedings of the International Symposium
◽
10.1615/ichmt.1995.radtransfprocheatmasstransfsevnuclreactacc.150
◽
1995
◽
Author(s):
Richard R. Hobbins
◽
Daniel J. Osetek
Keyword(s):
Fission Products
◽
Severe Accident
◽
Accident Conditions
Download Full-text
STATUS OF THE ESTER SEVERE ACCIDENT CODE SYSTEM
Proceedings of the International Symposium
◽
10.1615/ichmt.1995.radtransfprocheatmasstransfsevnuclreactacc.460
◽
1995
◽
Author(s):
A. V. Jones
◽
I. Shepherd
◽
M. Delaval
◽
J. Sangregorio
◽
S. Treta
Keyword(s):
Severe Accident
◽
Code System
Download Full-text
SAFETY ASSURANCE APPROACH TO SEVERE ACCIDENTS AND SEVERE ACCIDENT MANAGEMENT AT NUCLEAR POWER PLANTS WITH WWER
Proceedings of the International Symposium
◽
10.1615/ichmt.1995.radtransfprocheatmasstransfsevnuclreactacc.40
◽
1995
◽
Author(s):
V. A. Sidorenko
◽
V. Voznesenski
◽
N. Fil
◽
E. Tsygankov
Keyword(s):
Nuclear Power
◽
Power Plants
◽
Nuclear Power Plants
◽
Severe Accident
◽
Safety Assurance
◽
Severe Accidents
◽
Accident Management
Download Full-text
NUMERICAL SIMULATION OF TEMPERATURE FIELD IN STRATIFIED CORIUM AND EVALUATION OF NUCLEAR REACTOR WALL MELTING DURING SEVERE ACCIDENT
Proceeding of International Heat Transfer Conference 11
◽
10.1615/ihtc11.2120
◽
1998
◽
Author(s):
Leonid A. Dombrovsky
◽
Yuri Albertovich Zeigarnik
Keyword(s):
Numerical Simulation
◽
Temperature Field
◽
Nuclear Reactor
◽
Severe Accident
◽
Reactor Wall
Download Full-text
Application of two alternative shutdown severe accident management guideline (SSAMG) entry conditions for CPR1000
Kerntechnik
◽
10.3139/124.110960
◽
2019
◽
Vol 84
(1)
◽
pp. 22-28
Author(s):
Z. Huang
◽
H. Miao
◽
H. Hsieh
◽
N. Li
◽
D. Gu
Keyword(s):
Severe Accident
◽
Management Guideline
◽
Accident Management
Download Full-text
Post test calculations of a severe accident experiment for VVER-440 reactors by the ATHLET code
Kerntechnik
◽
10.3139/124.110380
◽
2013
◽
Vol 78
(4)
◽
pp. 362-370
Author(s):
H. György
◽
I. Trosztel
Keyword(s):
Severe Accident
◽
Post Test
Download Full-text
MELPROG-POW/MOD1: A two-dimensional, mechanistic code for analysis of reactor core melt progression and vessel attack under severe accident conditions
10.2172/6107175
◽
1989
◽
Author(s):
S. S. Dosanjh
Keyword(s):
Reactor Core
◽
Severe Accident
◽
Two Dimensional
◽
Accident Conditions
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