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Development of geopolymer based sacrificial materials for GEN IV severe accident mitigation
Journal of Nuclear Materials
◽
10.1016/j.jnucmat.2021.153024
◽
2021
◽
pp. 153024
Author(s):
Z. Černý
◽
T. Černoušek
◽
P. Vácha
◽
K. Sihelská
◽
V. Tyrpekl
Keyword(s):
Severe Accident
◽
Gen Iv
◽
Sacrificial Materials
Download Full-text
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References
Overview of the SAS4A Metallic Fuel Models and Extended Analysis of a Postulated Severe Accident in the Prototype Gen-IV Sodium-Cooled Fast Reactor
Nuclear Technology
◽
10.1080/00295450.2019.1636589
◽
2019
◽
Vol 206
(2)
◽
pp. 242-254
◽
Cited By ~ 1
Author(s):
A. M. Tentner
◽
A. Karahan
◽
S. H. Kang
Keyword(s):
Fast Reactor
◽
Severe Accident
◽
Metallic Fuel
◽
Fuel Models
◽
Extended Analysis
◽
Gen Iv
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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
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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
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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
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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
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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
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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
Download Full-text
Fission product release characteristics into containment under design basis and severe accident conditions
10.2172/6956680
◽
1988
◽
Author(s):
H. P. Nourbakhsh
◽
M. Khatib-Rahbar
◽
R. E. Davis
Keyword(s):
Fission Product
◽
Severe Accident
◽
Product Release
◽
Design Basis
◽
Accident Conditions
Download Full-text
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