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SOPHAEROS
SOPHAEROS is a computer code, used by the AECL and French Nuclear program to simulate the transfer of fission products in the reactor chamber. It…
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Computer simulation
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Review
2017
Review
2017
Benchmarking astec-na code capability to model source term within sfr containments
L. Herranz
,
M. R. García
,
L. Lebel
,
F. Mascari
,
C. Spengler
2017
Corpus ID: 196172920
espanolLa extension de las bases de diseno de los reactores de la Gen. IV a accidente severo plantea grandes desafios en la…
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2017
2017
Stand-alone containment analysis of the Phébus FPT-0 test with the ASTEC V 2 . 1 and the MELCOR v 2 . 2 codes
B. Gonfiottia
,
S. Pacia
2017
Corpus ID: 73596285
During the last 40 years, several efforts have been carried out to investigate the different phenomena occurring during a Severe…
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2010
2010
Chemistry of iodine and aerosol composition in the primary circuit of a nuclear power plant
M. Gouello
,
M. Lacoue-Nègre
,
+5 authors
C. Brémard
2010
Corpus ID: 54982654
In case of a severe accident on a nuclear reactor, radioactive iodine may be released into the environment, impacting…
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2008
2008
ASTEC V1.3 Code Assessment on the STORM Aerosols Mechanical Resuspension Tests
B. Tóth
,
R. Zeyen
2008
Corpus ID: 55984885
In most of the severe accident scenarios in light water reactors the deposition and resuspension of aerosols in the primary…
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2008
2008
Fission product modelling in ASTEC
M. Kissane
,
K. Liger
,
I. Drosik
,
H. Manenc
,
B. Schmitz
,
K. Trambauer
2008
Corpus ID: 34618237
Modelling fission product (FP) behaviour during severe light-water reactor accidents covers a considerable diversity of phenomena…
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2002
2002
Iodine Behaviour during severe Accidents
M. Petit
,
Y. Billarand
,
D. Jacquemain
,
N. Hanniet
,
E. Belval-Haltier
2002
Corpus ID: 30375413
This paper describes the current state of understanding of iodine behaviour based on these recent experimental results…
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1996
1996
SOPHAEROS code development and its application to falcon tests
G. Lajtha
,
M. Missirlian
,
M. Kissane
1996
Corpus ID: 172600136
One of the key issues in source-term evaluation in nuclear reactor severe accidents is determination of the transport behavior of…
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