设为首页
收藏本站
网站地图
|
English
|
公务邮箱
About the library
Background
History
Leadership
Organization
Readers' Guide
Opening Hours
Collections
Help Via Email
Publications
Electronic Information Resources
常用资源
电子图书
期刊论文
学位会议
外文资源
特色专题
内部出版物
SpringerLink电子期刊(15)
NATURE电子期刊(1)
Elsevier电子期刊(199)
ProQuest学位论文(2)
GSW全文库(1)
ACS电子期刊(1)
在“
Elsevier电子期刊
”中,
命中:
199
条,耗时:0.0139955 秒
在所有数据库中总计命中:
219
条
1.
A hybrid spectral nodal method for multigroup X,Y-geometry discrete ordinates eigenvalue problems
作者:
Davi José
;
M. Silva
;
Hermes Alves Filho
;
Ricardo C. Barros
;
rcbarros@pq.cnpq.br
关键词:
Nuclear reactor global
calculations
;
Discrete ordinates
;
Energy multigroup
;
Rectangular geometry
;
Eigenvalue problems
;
Hybrid spectral nodal method
刊名:Progress in Nuclear Energy
出版年:2017
2.
Review
calculations
for the OECD/NEA Burn-up Credit
Criticality
Safety Benchmark
作者:
José
;
J. Herrero
a
;
jose-javier.herrero@psi.ch" class="auth_mail" title="E-mail the corresponding author
;
Alexander Vasiliev
a
;
Marco Pecchia
a
;
Hakim Ferroukhi
a
;
Stefano Caruso
b
关键词:
Burn-up credit
;
MCNP6
;
SERPENT2
;
CINDER
;
Waste disposal
;
Criticality
safety
刊名:Annals of Nuclear Energy
出版年:2016
3.
Introducing time in derivation of the scaling factor for MCNP
criticality
calculations
作者:
Yang Yang
a
;
Min Chen
a
;
cm907@126.com" class="auth_mail" title="E-mail the corresponding author
;
Chunhai Lu
b
;
c
关键词:
MCNP
;
Criticality
calculation
;
Neutron flux
;
Scaling factor
刊名:Annals of Nuclear Energy
出版年:2016
4.
Criticality
calculations
of the Very High Temperature Reactor Critical Assembly benchmark with Serpent and SCALE/KENO-VI
作者:
Friederike Bostelmann
a
;
Friederike.Bostelmann@grs.de" class="auth_mail" title="E-mail the corresponding author
;
Hans R. Hammer
b
;
Javier Ortensi
c
;
Gerhard Strydom
c
;
Kiril Velkov
a
;
Winfried Zwermann
a
关键词:
HTGR
;
VHTRC
;
Serpent
;
SCALE/KENO-VI
刊名:Annals of Nuclear Energy
出版年:2016
5.
Nuclear data uncertainty for
criticality
-safety: Monte Carlo vs. linear perturbation
作者:
D. Rochman
a
;
;
A. Vasiliev
a
;
H. Ferroukhi
a
;
T. Zhu
b
;
S.C. van der Marck
c
;
A.J. Koning
d
;
e
关键词:
Criticality
benchmark
;
Nuclear data
;
Uncertainty
;
Sensitivity
刊名:Annals of Nuclear Energy
出版年:2016
6.
Criticality
validation of SuperMC with ICSBEP
作者:
Binhang Zhang
a
;
b
;
Jing Song
a
;
Guangyao Sun
a
;
Chaobin Chen
a
;
Liqin Hu
a
;
b
;
evanustc@mail.ustc.edu.cn" class="auth_mail" title="E-mail the corresponding author
关键词:
SuperMC
;
Criticality
;
Validation
;
ICSBEP
刊名:Annals of Nuclear Energy
出版年:2016
7.
Shielding calculation and
criticality
safety analysis of spent fuel transportation cask in research reactors
作者:
A. Mohammadi
a
;
M. Hassanzadeh
b
;
m_hassanzadeh2003@yahoo.com" class="auth_mail" title="E-mail the corresponding author
;
mhasanzadeh1354@gmail.com" class="auth_mail" title="E-mail the corresponding author
;
M. Gharib
c
关键词:
Shielding
;
Criticality
safety
;
Spent fuel
;
Transportation cask
;
Research Reactors
;
MCNP5 code
;
ORIGEN2.1 code
刊名:Applied Radiation and Isotopes
出版年:2016
8.
Monte Carlo
criticality
calculations
accelerated by a growing neutron population
作者:
Jan Dufek
a
;
jandufek@kth.se" class="auth_mail" title="E-mail the corresponding author
;
Kaur Tuttelberg
b
关键词:
Monte Carlo
criticality
;
Fission source
;
Convergence
;
Bias
;
Convergence acceleration
刊名:Annals of Nuclear Energy
出版年:2016
9.
Quantifying the effects of depletion parameters on the PWR spent fuel reactivity based on nuclide sensitivity coefficients
作者:
Rong-Jiun Sheu
a
;
b
;
rjsheu@mx.nthu.edu.tw" class="auth_mail" title="E-mail the corresponding author
;
Min-Hua Lee
a
;
Jenq-Horng Liang
a
;
b
关键词:
Spent fuel reactivity
;
Burnup credit
;
Nuclide sensitivity
;
Criticality
;
Fuel depletion
刊名:Annals of Nuclear Energy
出版年:2016
10.
Verification of MCNP6 model of the Jordan Research and Training Reactor (JRTR) for
calculations
of neutronic parameters
作者:
Mustafa K. Jaradat
a
;
mustafa.jaradat@jaec.gov.jo" class="auth_mail" title="E-mail the corresponding author
;
Vladimir Radulović
b
;
Chang Je Park
c
;
Luka Snoj
b
;
Salih M. Alkhafaji
a
关键词:
JRTR
;
Neutronic
;
Keff
;
Criticality
;
Flux
;
Monte Carlo
;
Research reactor
;
Power peaking factor
;
MCNP6
刊名:Annals of Nuclear Energy
出版年:2016
1
2
3
4
5
6
7
8
9
按检索点细分(199)
题名(28)
关键词(6)
文摘(162)
按出版年细分(199)
2027年及以后(16)
2017年(1)
2016年(17)
2013年(16)
2012年(17)
2011年(12)
2010年(16)
2009年(17)
2008年(10)
2007年(8)
2006年(9)
2005年(5)
2004年(6)
2003年(5)
2002年(8)
2001年(8)
2000年(5)
2000年及以前(23)
NGLC 2004-2010.National Geological Library of China All Rights Reserved.
Add:29 Xueyuan Rd,Haidian District,Beijing,PRC. Mail Add: 8324 mailbox 100083
For exchange or info please contact us via
email
.