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Volume 301

Nuclear Engineering and Design

Volume 301

1

Mechanical factors in primary water stress corrosion cracking of cold-worked stainless steel

Hammadi, Rashid Al, Yi, Yongsun, Zaki, Wael, Cho, Pyungyeon, Jang, Changheui

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 1.51 MB

english, 2016

2

Post shut-down decay heat removal from nuclear reactor core by natural convection loops in sodium pool

Rajamani, A., Sundararajan, T., Prasad, B.V.S.S.S., Parthasarathy, U., Velusamy, K.

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 6.19 MB

english, 2016

3

Signal analysis of acoustic and flow-induced vibrations of BWR main steam line

Espinosa-Paredes, G., Prieto-Guerrero, A., Núñez-Carrera, A., Vázquez-Rodríguez, A., Centeno-Pérez, J., Espinosa-Martínez, E.-G., Quezada-García, S., Cázares-Ramírez, R.

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 7.01 MB

english, 2016

4

A solver for the two-phase two-fluid model based on high-resolution total variation diminishing scheme

Abu Saleem, Rabie A., Kozlowski, Tomasz, Shrestha, Rijan

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 968 KB

english, 2016

5

The effect of external vertical acceleration on the dynamic behaviors of a single nuclear-coupled boiling channel

Lee, Jin-Der, Chen, Shao-Wen, Pan, Chin

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 3.08 MB

english, 2016

6

Monte Carlo modeling of Lead-Cooled Fast Reactor in adiabatic equilibrium state

Stanisz, Przemysław, Oettingen, Mikołaj, Cetnar, Jerzy

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 3.21 MB

english, 2016

7

CFD modelling of supercritical water flow and heat transfer in a 2×2 fuel rod bundle

Podila, Krishna, Rao, Yanfei

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 1.80 MB

english, 2016

8

Development of a thermal–mechanical behavior coupling analysis code for a dual-cooled annular fuel element in PWRs

Deng, Yangbin, Wu, Yingwei, Zhang, Dalin, Tian, Wenxi, Qiu, Suizheng, Su, G.H.

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 1.96 MB

english, 2016

9

Thermal modeling of a vertical dry storage cask for used nuclear fuel

Li, Jie, Liu, Yung Y.

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 5.20 MB

english, 2016

10

Design strength evaluation of RC beams under radiation environments for nuclear power plants

Kang, Won-Hee, Kwon, Tae-Hyun, Kim, Hyeong-Tae, Park, Kyoungsoo

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 881 KB

english, 2016

11

Application of Safety Instrumented System (SIS) approach in older nuclear power plants

Nasimi, Elnara, Gabbar, Hossam A.

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 2.50 MB

english, 2016

12

CFD modelling and validation of upward bubbly flow in an adiabatic vertical pipe using the quadrature method of moments

Peña-Monferrer, C., Passalacqua, A., Chiva, S., Muñoz-Cobo, J.L.

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 1.86 MB

english, 2016

13

Effective applied moment in circumferential through-wall cracked pipes for leak-before-break evaluation considering pipe restraint effects

Kim, Yeji, Hwang, Il-Soon, Oh, Young-Jin

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 1.21 MB

english, 2016

14

Fracture mechanics assessment of thermal aged nuclear piping based on the Leak-Before-Break concept

Chen, Mingya, Yu, Weiwei, Qian, Guian, Wang, Rongshan, Lu, Feng, Zhang, Guodong, Xue, Fei, Chen, Zhilin

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 1004 KB

english, 2016

15

Three-dimensional all-speed CFD code for safety analysis of nuclear reactor containment: Status of GASFLOW parallelization, model development, validation and application

Xiao, Jianjun, Travis, John R., Royl, Peter, Necker, Gottfried, Svishchev, Anatoly, Jordan, Thomas

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 8.95 MB

english, 2016

16

ANTEO+: A subchannel code for thermal-hydraulic analysis of liquid metal cooled systems

Lodi, F., Grasso, G., Mattioli, D., Sumini, M.

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 3.65 MB

english, 2016

17

Experimental study of heavy-liquid metal (LBE) flow and heat transfer along a hexagonal 19-rod bundle with wire spacers

Pacio, J., Daubner, M., Fellmoser, F., Litfin, K., Wetzel, Th.

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 4.83 MB

english, 2016

18

An enhanced fire hazard assessment model and validation experiments for vertical cable trays

Li, Lu, Huang, Xianjia, Bi, Kun, Liu, Xiaoshuang

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 1.03 MB

english, 2016

19

Computational fluid dynamics (CFD) round robin benchmark for a pressurized water reactor (PWR) rod bundle

Kang, Shin K., Hassan, Yassin A.

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 11.55 MB

english, 2016

20

Experimental study of effect of ambient flow condition on the performance of a passive autocatalytic recombiner

Liang, Zhe, Gardner, Lee, Clouthier, Tony, Thomas, Bryan

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 2.67 MB

english, 2016

21

Validating the BISON fuel performance code to integral LWR experiments

Williamson, R.L., Gamble, K.A., Perez, D.M., Novascone, S.R., Pastore, G., Gardner, R.J., Hales, J.D., Liu, W., Mai, A.

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 2.09 MB

english, 2016

22

Safeguards performance model for evaluation of potential safeguards strategies applied to pyroprocessing facilities

Riley, T.R., Pope, C.L., Benedict, R.W.

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 1.64 MB

english, 2016

23

Selection of optimal treatment procedures for non-standard radioactive waste arising from decommissioning of NPP after accident

Strážovec, Roman, Hrnčíř, Tomáš, Lištjak, Martin, Nečas, Vladimír

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 1.31 MB

english, 2016

24

Experimental simulation of fragmentation and stratification of core debris on the core catcher of a fast breeder reactor

Pillai, Dipin S., Vignesh, R., Sudha, A. Jasmin, Pushpavanam, S., Sundararajan, T., Nashine, B.K., Selvaraj, P.

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 2.21 MB

english, 2016

25

Containment leakage characterization with BARCOM test results for design and over pressure conditions

Mishra, Shubham, Thangamani, I., Singh, R.K.

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 2.03 MB

english, 2016

26

Development, verification and validation of an FPGA-based core heat removal protection system for a PWR

Wu, Yichun, Shui, Xuanxuan, Cai, Yuanfeng, Zhou, Junyi, Wu, Zhiqiang, Zheng, Jianxiang

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 2.84 MB

english, 2016

27

Experimental study on the minimum drag coefficient of supercritical pressure water in horizontal tubes

Lei, Xianliang, Li, Huixiong, Guo, YuMeng, Zhang, Qing, Zhang, Weiqiang, Zhang, Qian

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 4.14 MB

english, 2016

28

Numerical simulation of 2D ablation profile in CCI-2 experiment by moving particle semi-implicit method

Chai, Penghui, Kondo, Masahiro, Erkan, Nejdet, Okamoto, Koji

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 5.26 MB

english, 2016

29

Pressurized nuclear plant 10B abundance evolution study

Shijie, Tan, Ruping, Hu, Xiangming, Zhang, Zhijun, Li, Yang, Yuan

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 582 KB

english, 2016

30

Intuitional experiment and numerical analysis of flow characteristics affected by flow accelerated corrosion in elbow pipe system

Kim, Hyung Joon, Kim, Kyung Hoon

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 1.57 MB

english, 2016

31

Transient LOFA computations for a VHTR using one-twelfth core flow models

Tung, Yu-Hsin, Ferng, Yuh-Ming, Johnson, Richard W., Chieng, Ching-Chang

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 3.62 MB

english, 2016

32

Hydride precipitation, fracture and plasticity mechanisms in pure zirconium and Zircaloy-4 at temperatures typical for the postulated loss-of-coolant accident

Pshenichnikov, Anton, Stuckert, Juri, Walter, Mario

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 4.83 MB

english, 2016

33

Comparison of fission product release predictions using PARFUME with results from the AGR-1 safety tests

Collin, Blaise P., Petti, David A., Demkowicz, Paul A., Maki, John T.

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 2.39 MB

english, 2016