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CNKI会议论文(3)
CNKI学位论文(9)
知网期刊论文(22)
在“
Elsevier电子期刊
”中,
命中:
133
条,耗时:0.0300132 秒
在所有数据库中总计命中:
34
条
1.
Evaluation of hydraulic characteristics of core flow monitoring mechanism for PFBR
作者:
N.S. Shivakumar
;
Nagaraju Bekkenti
;
nagarajub@igcar.gov.in
;
S. Suresh Kumar
;
N. Ravichandran
;
V. Vinod
;
G. Padmakumar
;
K.K. Rajan
关键词:
Prototype
Fast
Breeder
Reactor
;
Fuel subassembly
;
Eddy current flow sensor
;
Core flow measurement
刊名:Annals of Nuclear Energy
出版年:2017
2.
Feasibility of ANFIS towards multiclass event classification in PFBR considering dimensionality reduction using PCA
作者:
Manas Ranjan Prusty
a
;
manas.iter144@gmail.com" class="auth_mail" title="E-mail the corresponding author
;
T. Jayanthi
a
;
Jaideep Chakraborty
a
;
K. Velusamy
b
关键词:
Prototype
fast
breeder
reactor
;
Adaptive neuro fuzzy inference system
;
Principal component analysis
;
Dimensionality reduction
;
Factor analysis
刊名:Annals of Nuclear Energy
出版年:2017
3.
Reliability analysis of Diesel Generator power supply system of
Prototype
Fast
Breeder
Reactor
作者:
Pramod Kumar Sharma
;
pramodks@igcar.gov.in
;
V. Bhuvana
;
M. Ramakrishnan
关键词:
PFBR
;
Prototype
Fast
Breeder
Reactor
;
FBTR
;
Fast
Breeder
Test
Reactor
;
CB
;
Circuit Breaker
;
SBO
;
Station Blackout
;
FTA
;
Fault Tree Analysis
;
CCF
;
common cause failure
;
DG
;
Diesel Generators
;
EMTR
;
Emergency Mean Transfer Relay
;
SSWS
;
Safety related service water system
;
EF
;
Error Factor
;
RCB
;
Reactor
Containment Building
;
PCC
;
Power Control Centres
;
MTTR
;
mean time to repair
;
NICB
;
Nuclear Island Connected Building
;
LT
;
low tension
;
PSA
;
probabilistic safety assessment
刊名:Nuclear Engineering and Design
出版年:2016
4.
Design and performance evaluation of Core Flow Monitoring Mechanisms for PFBR
作者:
Muhammad Sabih
;
sabih@igcar.gov.in" class="auth_mail" title="E-mail the corresponding author
;
S. Sureshkumar
;
Sudheer Patri
;
N.S. Shivakumar
;
N. Ravichandran
;
C.L. Thakur
;
Vishal D. Paunikar
;
R. Vijayashree
;
V.A. Sureshkumar
;
C. Meikandamurthy
;
I.B. Noushad
;
G. Padmakumar
;
V. Prakash
;
K.K. Rajan
关键词:
Eddy Current Flow Sensor
;
Core Flow Monitoring Mechanism
;
Flow guide
;
Sub-assembly
;
Leakage flow
;
Prototype
Fast
Breeder
Reactor
刊名:Annals of Nuclear Energy
出版年:2016
5.
Experimental studies in water for safety grade decay heat removal of
prototype
fast
breeder
reactor
作者:
V.M. Mente
;
G.K. P
;
ey
;
I. Banerjee
;
S. Ajesh Kumar
;
G. Padmakumar
;
K.K. Rajan
关键词:
Decay hear removal system
;
Natural circulation
;
Inter wrapper flow
;
Fast
breeder
reactor
;
Richardson number
刊名:Annals of Nuclear Energy
出版年:March, 2014
6.
Ultrasonic decontamination of
prototype
fast
breeder
reactor
fuel pins
作者:
Aniruddha Kumar
;
R.B. Bhatt
;
P.G. Behere
;
Mohd. Afzal
关键词:
Ultrasonic
;
Decontamination
;
Radio-active
;
MOX fuel pin
;
Fast
reactor
刊名:Ultrasonics
出版年:April, 2014
7.
Uncertainty evaluation of reliability of safety grade decay heat removal system of Indian
prototype
fast
breeder
reactor
作者:
H.L. Kumawat
;
Om Pal Singh
;
Prabhat Munshi
关键词:
Uncertainty analysis
;
Safety grade decay heat removal system
;
Prototype
fast
breeder
reactor
;
Fault tree
;
Reliability analysis
刊名:Annals of Nuclear Energy
出版年:2013
8.
High Temperature Materials for Nuclear
Fast
Fission and Fusion
Reactor
s and Advanced Fossil Power Plants
作者:
T. Jayakumar
;
tjk@igcar.gov.in
;
M.D. Mathew
;
K. Laha
关键词:
Creep
;
low cycle fatigue
;
fast
reactor
;
fusion
reactor
;
AUSC
刊名:Procedia Engineering
出版年:2013
9.
A multi layer core catcher concept for future sodium cooled
fast
reactor
s
作者:
A. Jasmin Sudha
;
K. Velusamy
;
P. Chellap
i
关键词:
Core catcher
;
Multi layer
;
Delay bed
;
Ceramics
;
Safety analysis
;
Whole core melt down
刊名:Annals of Nuclear Energy
出版年:March, 2014
10.
Dynamic modeling of steam water system of
prototype
fast
breeder
reactor
using RELAP code
作者:
Prashant Sharma
;
K. Natesan
;
P. Selvaraj
;
pselva@igcar.gov.in" class="auth_mail
;
V. Balasubramaniyan
;
P. Chellapandi
关键词:
PFBR
;
BoP system
;
RELAP5
;
Plant dynamics
刊名:Annals of Nuclear Energy
出版年:June, 2014
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