Volume 108

Annals of Nuclear Energy

Volume 108

1

Reloading pattern optimization of VVER-1000 reactors in transient cycles using genetic algorithm

Rahmani, Yashar

Journal:

Annals of Nuclear Energy

Year:

2017

Language:

english

File:

PDF, 7.88 MB

english, 2017

2

Non-linear boiling water reactor stability with Shannon Entropy

Olvera-Guerrero, Omar Alejandro, Prieto-Guerrero, Alfonso, Espinosa-Paredes, Gilberto

Journal:

Annals of Nuclear Energy

Year:

2017

Language:

english

File:

PDF, 1.96 MB

english, 2017

3

Structural analysis of the CAREM-25 nuclear power plant subjected to the design basis accident and seismic loads

Ambrosini, Daniel, Codina, Ramón H., Curadelli, Oscar, Martínez, Carlos A.

Journal:

Annals of Nuclear Energy

Year:

2017

Language:

english

File:

PDF, 5.49 MB

english, 2017

4

A study of reactivity biases and their dependence on spatial discretization in depleted TRIGA fuel

Cheng, Ye, Roberts, Jeremy A.

Journal:

Annals of Nuclear Energy

Year:

2017

Language:

english

File:

PDF, 1.25 MB

english, 2017

5

Generalized Iterated Fission Probability for Monte Carlo eigenvalue calculations

Terranova, Nicholas, Zoia, Andrea

Journal:

Annals of Nuclear Energy

Year:

2017

Language:

english

File:

PDF, 1.32 MB

english, 2017

6

Effect of in-core instrumentation mounting location on external reactor vessel cooling

Suh, Jungsoo, Ha, Huiun

Journal:

Annals of Nuclear Energy

Year:

2017

Language:

english

File:

PDF, 3.11 MB

english, 2017

7

Status of dynamic water film model development in 3-D CFD code GASFLOW-MPI for analysis of passive containment cooling system

Xiao, Jianjun, Travis, Jack, Bottoni, Maurizio

Journal:

Annals of Nuclear Energy

Year:

2017

Language:

english

File:

PDF, 3.38 MB

english, 2017

8

Investigation on two-phase distribution in a vibrating annulus

Xiao, Xiu, Zhu, Qingzi, Chen, Shao-Wen, Zhang, Yajun, Jia, Haijun, Ishii, Mamoru

Journal:

Annals of Nuclear Energy

Year:

2017

Language:

english

File:

PDF, 2.53 MB

english, 2017

9

Scaling analysis of the spreading and deposition behaviors of molten-core-simulated metals

Matsumoto, Tatsuki, Sakurada, Keishi, Miwa, Shuichiro, Sakashita, Hiroto, Mori, Michitsugu

Journal:

Annals of Nuclear Energy

Year:

2017

Language:

english

File:

PDF, 1.91 MB

english, 2017

10

Core optimisation issues of MOX fueled ALLEGRO reactor

Pónya, P., Czifrus, Sz.

Journal:

Annals of Nuclear Energy

Year:

2017

Language:

english

File:

PDF, 2.29 MB

english, 2017

11

Transient analysis of AP1000 NPP under the similar Fukushima accident conditions

Yang, Jiang, Liang, Ren, Lin, Zhikang, Huang, Xi, Wang, Ting

Journal:

Annals of Nuclear Energy

Year:

2017

Language:

english

File:

PDF, 1.26 MB

english, 2017

12

Failure mode taxonomy for assessing the reliability of Field Programmable Gate Array based Instrumentation and Control systems

McNelles, Phillip, Zeng, Zhao Chang, Renganathan, Guna, Chirila, Marius, Lu, Lixuan

Journal:

Annals of Nuclear Energy

Year:

2017

Language:

english

File:

PDF, 2.08 MB

english, 2017

13

Modeling of FREYA fast critical experiments with the Serpent Monte Carlo code

Fridman, E., Kochetkov, A., Krása, A.

Journal:

Annals of Nuclear Energy

Year:

2017

Language:

english

File:

PDF, 5.42 MB

english, 2017

14

The virtual simulation system for training and demonstrating the design of the head-end of spent nuclear fuel reprocessing

ZHongkun, Liu, Qiang, ZHao, Haishan, Zhu, Peitao, Song

Journal:

Annals of Nuclear Energy

Year:

2017

Language:

english

File:

PDF, 1.57 MB

english, 2017

15

Stand-alone core sensitivity and uncertainty analysis of ALFRED from Monte Carlo simulations

Pérez-Valseca, A.-D., Espinosa-Paredes, G., François, J.L., Vázquez Rodríguez, A., Martín-del-Campo, C.

Journal:

Annals of Nuclear Energy

Year:

2017

Language:

english

File:

PDF, 4.52 MB

english, 2017

16

Unsteady-state thermal stress and thermal deformation analysis for a pressurizer surge line subjected to thermal stratification based on a coupled CFD-FEM method

Zhang, Y., Lu, T.

Journal:

Annals of Nuclear Energy

Year:

2017

Language:

english

File:

PDF, 4.30 MB

english, 2017

17

Theoretical analysis and evaluation for neutron-induced reaction on 239 Pu

Guo, Hairui, Han, Yinlu, Ye, Tao, Sun, Weili, Cai, Chonghai

Journal:

Annals of Nuclear Energy

Year:

2017

Language:

english

File:

PDF, 4.76 MB

english, 2017

18

An advanced new fully implicit numerical method for two-phase flow subchannel analysis based on the Drift Flux Model

Hajizadeh, A., Kazeminejad, H., Talebi, S.

Journal:

Annals of Nuclear Energy

Year:

2017

Language:

english

File:

PDF, 3.21 MB

english, 2017

19

A hybrid pile oscillator experiment in the Minerve reactor

Geslot, Benoit, Gruel, Adrien, Walczak, Piotr, Leconte, Pierre, Blaise, Patrick

Journal:

Annals of Nuclear Energy

Year:

2017

Language:

english

File:

PDF, 2.43 MB

english, 2017

20

Improved discrete nodal transport method for treating void regions

Xu, Zhitao, Wu, Hongchun, Li, Yunzhao, Zheng, Youqi

Journal:

Annals of Nuclear Energy

Year:

2017

Language:

english

File:

PDF, 1.24 MB

english, 2017

21

Inverse kinetics for subcritical systems with external neutron source

de Carvalho Gonçalves, Wemerson, Martinez, Aquilino Senra, da Silva, Fernando Carvalho

Journal:

Annals of Nuclear Energy

Year:

2017

Language:

english

File:

PDF, 1.27 MB

english, 2017

22

Flow and heat transfer analyses of a plate-fin heat exchanger in an HTGR

Chen, Tao, Wang, Jie, Peng, Wei

Journal:

Annals of Nuclear Energy

Year:

2017

Language:

english

File:

PDF, 5.70 MB

english, 2017

23

A full life cycle nuclear knowledge management framework based on digital system

Wang, Minglu, Zheng, Mingguang, Tian, Lin, Qiu, Zhongming, Li, Xiaoyan

Journal:

Annals of Nuclear Energy

Year:

2017

Language:

english

File:

PDF, 2.02 MB

english, 2017

24

Estimation of axial xenon oscillations with online parameter adaptation in the P.W.R nuclear reactors using Lyapunov approach based on the multipoint kinetics reactor model

Zaidabadi nejad, M., Ansarifar, G.R.

Journal:

Annals of Nuclear Energy

Year:

2017

Language:

english

File:

PDF, 5.50 MB

english, 2017

25

Comparison of ASME pressure–temperature limits on the fracture probability for a pressurized water reactor pressure vessel

Chou, Hsoung-Wei, Huang, Chin-Cheng

Journal:

Annals of Nuclear Energy

Year:

2017

Language:

english

File:

PDF, 2.65 MB

english, 2017

26

Multi-hazard performance of reinforced concrete dry casks subjected to chloride attack and tip-over impact

Hanifehzadeh, Mohammad, Gencturk, Bora, Attar, Arezou, Willam, Kaspar

Journal:

Annals of Nuclear Energy

Year:

2017

Language:

english

File:

PDF, 4.30 MB

english, 2017

27

Solution of the neutron transport equation by the Method of Characteristics using a linear representation of the source within a mesh

Mazumdar, Tanay, Degweker, S.B.

Journal:

Annals of Nuclear Energy

Year:

2017

Language:

english

File:

PDF, 7.26 MB

english, 2017

28

A comparative study of station blackout scenario dynamics initiated by internal and seismic event in boiling water reactor

Park, Sanggil, Lee, Jaeyoung

Journal:

Annals of Nuclear Energy

Year:

2017

Language:

english

File:

PDF, 1.49 MB

english, 2017

29

A study of insider threat in nuclear security analysis using game theoretic modeling

Kim, Kyo-Nam, Yim, Man-Sung, Schneider, Erich

Journal:

Annals of Nuclear Energy

Year:

2017

Language:

english

File:

PDF, 1.32 MB

english, 2017

30

The ADO-nodal method for solving two-dimensional discrete ordinates transport problems

Barichello, L.B., Picoloto, C.B., da Cunha, R.D.

Journal:

Annals of Nuclear Energy

Year:

2017

Language:

english

File:

PDF, 462 KB

english, 2017

31

Thermal performance of a concrete cask: Methodology to model helium leakage from the steel canister

Penalva, J., Feria, F., Herranz, L.E.

Journal:

Annals of Nuclear Energy

Year:

2017

Language:

english

File:

PDF, 2.44 MB

english, 2017

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