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Volume 318

Nuclear Engineering and Design

Volume 318

1

TRIGLAV: A program package for TRIGA reactor calculations

Peršič, Andreja, Žagar, Tomaž, Ravnik, Matjaž, Slavič, Slavko, Žefran, Bojan, Ćalić, Dušan, Trkov, Andrej, Žerovnik, Gašper, Jazbec, Anže, Snoj, Luka

Journal:

Nuclear Engineering and Design

Année:

2017

Langue:

english

Fichier:

PDF, 3.87 MB

english, 2017

2

RELAP5 simulation of CANDU Station Blackout accidents with/without water make-up to the steam generators

Zhou, Feng, Novog, David R.

Journal:

Nuclear Engineering and Design

Année:

2017

Langue:

english

Fichier:

PDF, 6.49 MB

english, 2017

3

A novel multi-scale domain overlapping CFD/STH coupling methodology for multi-dimensional flows relevant to nuclear applications

Grunloh, T.P., Manera, A.

Journal:

Nuclear Engineering and Design

Année:

2017

Langue:

english

Fichier:

PDF, 6.04 MB

english, 2017

4

Experimental study for pressure drop and flow instability of two-phase flow in the PCHE-type steam generator for SMRs

Shin, Chang Wook, NO, Hee Cheon

Journal:

Nuclear Engineering and Design

Année:

2017

Langue:

english

Fichier:

PDF, 1.34 MB

english, 2017

5

Convective heat transfer at high subcritical pressures in tubes with and without flow obstacles

Eter, Ahmad, Groeneveld, Dé, Tavoularis, Stavros

Journal:

Nuclear Engineering and Design

Année:

2017

Langue:

english

Fichier:

PDF, 9.46 MB

english, 2017

6

Development of NUFORM3D module with FRAPCON3.4 for simulation of pellet-cladding mechanical interaction

Kim, Hyo Chan, Seo, Sang Kyu, Lee, Sung Uk, Yang, Yong Sik

Journal:

Nuclear Engineering and Design

Année:

2017

Langue:

english

Fichier:

PDF, 4.70 MB

english, 2017

7

Heat & mass transfer and interface temperature during simulated melt-concrete interaction with composition variation in ARTEMIS 2D experiment

Pham, Q.T., Seiler, J.M., Combeau, H.

Journal:

Nuclear Engineering and Design

Année:

2017

Langue:

english

Fichier:

PDF, 3.69 MB

english, 2017

8

Numerical simulations of liquid spreading and fires following an aircraft impact

Sikanen, Topi, Hostikka, Simo

Journal:

Nuclear Engineering and Design

Année:

2017

Langue:

english

Fichier:

PDF, 2.55 MB

english, 2017

9

Thermal fatigue damage assessment at mixing tees (elastic-plastic deformation effect on stress and strain fluctuations)

Kamaya, Masayuki, Miyoshi, Koji

Journal:

Nuclear Engineering and Design

Année:

2017

Langue:

english

Fichier:

PDF, 4.10 MB

english, 2017

10

Thermal-hydraulic comparisons of 19-pin rod bundles with four circular and trapezoid shaped wire wraps

Liu, Li, Wang, Shan, Bai, Bofeng

Journal:

Nuclear Engineering and Design

Année:

2017

Langue:

english

Fichier:

PDF, 6.42 MB

english, 2017

11

Seismic mitigation performance and optimization design of NPP water tank with internal ring baffles under earthquake loads

Zhao, Chunfeng, Chen, Jianyun, Wang, Jingfeng, Yu, Na, Xu, Qiang

Journal:

Nuclear Engineering and Design

Année:

2017

Langue:

english

Fichier:

PDF, 6.32 MB

english, 2017

12

Performance evaluation of decay heat removal system of PFBR with partial availability of air side dampers

Vinod, V., Sathishkumar, S., Mourya, R.K., Chandramouli, S., Padmakumar, G., Nashine, B.K., Selvaraj, P.

Journal:

Nuclear Engineering and Design

Année:

2017

Langue:

english

Fichier:

PDF, 1.20 MB

english, 2017

13

The effect of coupled wear and creep during grid-to-rod fretting

Wang, Hai, Hu, Zupan, Lu, Wei, Thouless, M.D.

Journal:

Nuclear Engineering and Design

Année:

2017

Langue:

english

Fichier:

PDF, 3.37 MB

english, 2017

14

Parameter analysis of neutron point kinetics for nuclear reactors

El_Tokhy, Mohamed S., Mahmoud, Imbaby I.

Journal:

Nuclear Engineering and Design

Année:

2017

Langue:

english

Fichier:

PDF, 5.34 MB

english, 2017

15

Experimental evaluation of safety performance of emergency passive residual heat removal system in HPR1000

Sun, D.C., Li, Y., Xi, Z., Zan, Y.F., Li, P.Z., Zhuo, W.B.

Journal:

Nuclear Engineering and Design

Année:

2017

Langue:

english

Fichier:

PDF, 1.32 MB

english, 2017

16

An experimental parametric study on natural circulation BWRs stability

Marcel, Christian P., Rohde, M., Van Der Hagen, T.H.J.J.

Journal:

Nuclear Engineering and Design

Année:

2017

Langue:

english

Fichier:

PDF, 1.74 MB

english, 2017

17

An investigation of pool entrainment based on the method of Volume of Fluid

Lu, Meng, Xie, Heng

Journal:

Nuclear Engineering and Design

Année:

2017

Langue:

english

Fichier:

PDF, 3.22 MB

english, 2017

18

Development of a semi-empirical cladding oxidation model and verification by BWR & VVER type CORA tests

Ni, Xinghe, Wong, Kin-Wah, Wu, Jingjin, Zheng, Jianxiang, Li, Ning

Journal:

Nuclear Engineering and Design

Année:

2017

Langue:

english

Fichier:

PDF, 4.36 MB

english, 2017

19

Calculation of the C5G7 3-D extension benchmark by ARES transport code

Zhang, Liang, Zhang, Bin, Liu, Cong, Zheng, Junxiao, Zheng, Ying, Chen, Yixue

Journal:

Nuclear Engineering and Design

Année:

2017

Langue:

english

Fichier:

PDF, 2.46 MB

english, 2017