Volume 272

Nuclear Engineering and Design

Volume 272

1

ASTEC application for in-vessel melt retention modelling in VVER plants

Zvonarev, Yu.A., Volchek, A.M., Kobzar, V.L., Budaev, M.A.

Journal:

Nuclear Engineering and Design

Year:

2014

Language:

english

File:

PDF, 1.81 MB

english, 2014

2

Models for fuel porosity evolution in UO2 under various regimes of reactor operation

Tarasov, V.I., Veshchunov, M.S.

Journal:

Nuclear Engineering and Design

Year:

2014

Language:

english

File:

PDF, 2.59 MB

english, 2014

3

Experimental and numerical study of stratification and solidification/melting behaviors

Li, Gen, Oka, Yoshiaki, Furuya, Masahiro

Journal:

Nuclear Engineering and Design

Year:

2014

Language:

english

File:

PDF, 4.02 MB

english, 2014

4

Analysis of the horizontal flow in the advanced gas-cooled reactor

Duan, Y., He, S., Ganesan, P., Gotts, J.

Journal:

Nuclear Engineering and Design

Year:

2014

Language:

english

File:

PDF, 3.94 MB

english, 2014

5

Convective heat transfer in a semi-closed BWR-fuel assembly in absence of water

Schulz, S., Schuster, C., Hurtado, A.

Journal:

Nuclear Engineering and Design

Year:

2014

Language:

english

File:

PDF, 699 KB

english, 2014

6

The oxidation behavior of three different zones of welded Incoloy 800H alloy

Chen, W.S., Kai, W., Tsay, L.W., Kai, J.J.

Journal:

Nuclear Engineering and Design

Year:

2014

Language:

english

File:

PDF, 3.81 MB

english, 2014

7

A numerical solution to the point kinetic equations using Taylor–Lie series combined with a scaling and squaring technique

Kim, Hak Tae, Park, Yujin, Kazantzis, Nikolaos, Parlos, Alexander G., Vista, Felipe P., Chong, Kil To

Journal:

Nuclear Engineering and Design

Year:

2014

Language:

english

File:

PDF, 1.08 MB

english, 2014

8

Combining models of behaviour with operational data to provide enhanced condition monitoring of AGR cores

West, Graeme M., Wallace, Christopher J., McArthur, Stephen D.J.

Journal:

Nuclear Engineering and Design

Year:

2014

Language:

english

File:

PDF, 2.53 MB

english, 2014

9

Modeling and controllers design of the China CLEAR-IB

Yan, Shoujun, Wang, Pengfei, Wan, Jiashuang, Sun, Changyi, Zhao, Fuyu

Journal:

Nuclear Engineering and Design

Year:

2014

Language:

english

File:

PDF, 1.56 MB

english, 2014

10

Accident analyses for china pressurizer reactor with an innovative conceptual design of passive residual heat removal system

Wang, Mingjun, Zhang, Dalin, Qiu, Suizheng, Tian, Wenxi, Su, Guanghui

Journal:

Nuclear Engineering and Design

Year:

2014

Language:

english

File:

PDF, 3.00 MB

english, 2014

11

Structural integrity assessment of the reactor pressure vessel under the pressurized thermal shock loading

Chen, Mingya, Lu, Feng, Wang, Rongshan, Ren, Ai

Journal:

Nuclear Engineering and Design

Year:

2014

Language:

english

File:

PDF, 1.46 MB

english, 2014

12

Irradiation embrittlement assessment and prediction of Armenian NPP reactor pressure vessel steels

Kryukov, A., Sevikyan, G., Petrosyan, V., Vardanyan, A.

Journal:

Nuclear Engineering and Design

Year:

2014

Language:

english

File:

PDF, 2.01 MB

english, 2014

13

Validation of ASTEC V2 models for the behaviour of corium in the vessel lower head

Carénini, L., Fleurot, J., Fichot, F.

Journal:

Nuclear Engineering and Design

Year:

2014

Language:

english

File:

PDF, 3.27 MB

english, 2014

14

Assessment on 900–1300MWe PWRs of the ASTEC-based simulation tool of SGTR thermal-hydraulics for the IRSN Emergency Technical Centre

Foucher, L., Cousin, F., Fleurot, J., Brethes, S.

Journal:

Nuclear Engineering and Design

Year:

2014

Language:

english

File:

PDF, 4.10 MB

english, 2014

15

ASTEC V2.0 reactor applications on French PWR 900MWe accident sequences and comparison with MAAP4

Lombard, Virginie, Azarian, Garo, Ducousso, Erik, Gandrille, Pascal

Journal:

Nuclear Engineering and Design

Year:

2014

Language:

english

File:

PDF, 1.80 MB

english, 2014

16

Editorial

VAN DORSSELAERE, Jean-Pierre, Bonnet, J.M., Jacquemain, D., Haste, T.

Journal:

Nuclear Engineering and Design

Year:

2014

Language:

english

File:

PDF, 115 KB

english, 2014

17

Source term assessment with ASTEC and associated uncertainty analysis using SUNSET tool

Chevalier-Jabet, K., Cousin, F., Cantrel, L., Séropian, C.

Journal:

Nuclear Engineering and Design

Year:

2014

Language:

english

File:

PDF, 3.34 MB

english, 2014

18

Continuous validation of ASTEC containment models and regression testing

Nowack, Holger, Reinke, Nils, Sonnenkalb, Martin

Journal:

Nuclear Engineering and Design

Year:

2014

Language:

english

File:

PDF, 3.87 MB

english, 2014

19

ASTEC V2 severe accident integral code: Fission product modelling and validation

Cantrel, L., Cousin, F., Bosland, L., Chevalier-Jabet, K., Marchetto, C.

Journal:

Nuclear Engineering and Design

Year:

2014

Language:

english

File:

PDF, 2.20 MB

english, 2014

20

Validation of ASTEC core degradation and containment models

Kruse, Philipp, Brähler, Thimo, Koch, Marco K.

Journal:

Nuclear Engineering and Design

Year:

2014

Language:

english

File:

PDF, 2.72 MB

english, 2014

21

ASTEC investigations of severe core damage behaviour of VVER-1000 in case of loss of coolant accident along with Station-Black-Out

Groudev, Pavlin, Atanasova, Boryana, Chatterjee, Barun, Lele, Hemant G.

Journal:

Nuclear Engineering and Design

Year:

2014

Language:

english

File:

PDF, 934 KB

english, 2014

22

ASTEC adaptation for PHWR limited core damage accident analysis

Majumdar, P., Chatterjee, B., Lele, H.G., Guillard, G., Fichot, F.

Journal:

Nuclear Engineering and Design

Year:

2014

Language:

english

File:

PDF, 2.14 MB

english, 2014

23

The predicted effects of selected Phebus FPT1 sump constituents on iodine volatility

Cripps, R.C., Güntay, S., Jäckel, B.

Journal:

Nuclear Engineering and Design

Year:

2014

Language:

english

File:

PDF, 1010 KB

english, 2014

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