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常用资源
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内部出版物
CNKI学位论文(22)
知网期刊论文(16)
在“
Elsevier电子期刊
”中,
命中:
7
条,耗时:0.0229893 秒
在所有数据库中总计命中:
38
条
1.
Historical insights in the development of Best Estimate Plus
Uncertainty
safety analysis
作者:
Gary E. Wilson
;
katJon@ida.net
关键词:
BEPU
;
Best Estimate Plus
Uncertainty
;
CSAU
;
code
scaling
applicability
and
uncertainty
;
CFR
;
code
of federal regulations
;
DBA
;
design basis accident
;
LBLOCA
;
large break loss of coolant accident
;
NPP
;
nuclear power plant
;
PDF
;
probability density function
刊名:Annals of Nuclear Energy
出版年:2013
2.
Use of forward sensitivity analysis method to improve
code
scaling
,
applicability
,
and
uncertainty
(CSAU) methodology
作者:
Haihua Zhao
a
;
Haihua.Zhao@inl.gov
;
Vincent A. Mousseau
b
刊名:Nuclear Engineering
and
Design
出版年:2012
3.
On the CSAU employment during ULOF accident initiating phase for sodium-cooled fast reactors
作者:
M. Pellegrini
a
;
pellegrini.m.aa@m.titech.ac.jp
;
H. Endo
b
;
endo-hiroshi@jnes.go.jp
;
H. Ninokata
a
;
hninokat@nr.titech.ac.jp
刊名:Nuclear Engineering
and
Design
出版年:2012
4.
Prediction of debris flow inundation areas using empirical mobility relationships
作者:
Matteo Berti
;
Aless
;
ro Simoni
关键词:
Debris flows
;
Hazard
;
Empirical relationships
;
Italian Alps
刊名:Geomorphology
出版年:2007
5.
AREVA's realistic large break LOCA analysis methodology
作者:
Martin
;
Robert P.
;
OaaaDell
;
Larry D.
刊名:Nuclear Engineering
and
Design
出版年:2005
6.
Application of
code
scaling
applicability
and
uncertainty
methodology to the large break loss of coolant
作者:
Young
;
M.Y.
;
Bajorek
;
S.M.
;
Nissley
;
M.E.
;
Hochreiter
;
L.E.
刊名:Nuclear Engineering
and
Design
出版年:1998
7.
The role of the PIRT process in experiments,
code
development
and
code
applications associated with reactor safety analysis
作者:
Wilson
;
Gary E.
;
Boyack
;
Brent E.
刊名:Nuclear Engineering
and
Design
出版年:1998
1
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