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Volume 347

Nuclear Engineering and Design

Volume 347

1

Quenching experiment on Cr-alloy-coated cladding for accident-tolerant fuel in water pool under low and high subcooling conditions

Lee, Kwan-Geun, In, Wang-Kee, Kim, Hyun-Gil

Journal:

Nuclear Engineering and Design

Année:

2019

Fichier:

PDF, 9.18 MB

2019

2

Influences of some engineered factors on IVR-ERVC limits

Kuang, Bo, Liu, Pengfei, Wang, Fan, Cao, Kemei, Zhang, Kun

Journal:

Nuclear Engineering and Design

Année:

2019

Fichier:

PDF, 1.39 MB

2019

3

Slope monitoring system for nuclear power plants

Lee, Yonghee, Choi, Weon-Hack, Kim, Seok-Chul

Journal:

Nuclear Engineering and Design

Année:

2019

Fichier:

PDF, 13.56 MB

2019

4

Fully ceramic microencapsulated fuel in prismatic high-temperature gas-cooled reactors: Design basis accidents and fuel cycle cost

Lu, Cihang, Brown, Nicholas R.

Journal:

Nuclear Engineering and Design

Année:

2019

Fichier:

PDF, 4.13 MB

2019

5

Quenching experiment on Cr-alloy-coated cladding for accident-tolerant fuel in water pool under low and high subcooling conditions

Lee, Kwan-Geun, In, Wang-Kee, Kim, Hyun-Gil

Journal:

Nuclear Engineering and Design

Année:

2019

Langue:

english

Fichier:

PDF, 9.18 MB

english, 2019

6

Revaluation of the aging property modification factor of lead rubber bearings based on accelerated aging tests and finite element analysis

Park, Junhee, Choun, Young-Sun, Kim, Min Kyu, Hahm, Daegi

Journal:

Nuclear Engineering and Design

Année:

2019

Langue:

english

Fichier:

PDF, 2.77 MB

english, 2019

7

Influences of some engineered factors on IVR-ERVC limits

Kuang, Bo, Liu, Pengfei, Wang, Fan, Cao, Kemei, Zhang, Kun

Journal:

Nuclear Engineering and Design

Année:

2019

Langue:

english

Fichier:

PDF, 1.39 MB

english, 2019

8

Slope monitoring system for nuclear power plants

Lee, Yonghee, Choi, Weon-Hack, Kim, Seok-Chul

Journal:

Nuclear Engineering and Design

Année:

2019

Langue:

english

Fichier:

PDF, 13.56 MB

english, 2019

9

Fully ceramic microencapsulated fuel in prismatic high-temperature gas-cooled reactors: Design basis accidents and fuel cycle cost

Lu, Cihang, Brown, Nicholas R.

Journal:

Nuclear Engineering and Design

Année:

2019

Langue:

english

Fichier:

PDF, 4.13 MB

english, 2019

10

Pool stratification and mixing induced by steam injection through spargers: CFD modelling of the PPOOLEX and PANDA experiments

Gallego-Marcos, Ignacio, Kudinov, Pavel, Villanueva, Walter, Kapulla, Ralf, Paranjape, Sidharth, Paladino, Domenico, Laine, Jani, Puustinen, Markku, Räsänen, Antti, Pyy, Lauri, Kotro, Eetu

Journal:

Nuclear Engineering and Design

Année:

2019

Langue:

english

Fichier:

PDF, 19.85 MB

english, 2019

11

Experimental investigation of radiation heat transfer in coolant channel under impaired cooling scenario for Indian PHWR

Ajay, Ketan, Kumar, Ravi, Mukhopadhyay, Deb, Gupta, Akhilesh, Das, Arup K., Gokhale, Onkar

Journal:

Nuclear Engineering and Design

Année:

2019

Langue:

english

Fichier:

PDF, 2.76 MB

english, 2019

12

Three-dimensional numerical simulation of the HECLA-4 transient MCCI experiment by improved MPS method

Chen, Ronghua, Cai, Qinghang, Zhang, Penghui, Li, Yonglin, Guo, Kailun, Tian, Wenxi, Qiu, Suizheng, Su, G.H.

Journal:

Nuclear Engineering and Design

Année:

2019

Langue:

english

Fichier:

PDF, 4.90 MB

english, 2019

13

A review of history parameters in PWR core analysis

Szames, Esteban, Tomatis, Daniele

Journal:

Nuclear Engineering and Design

Année:

2019

Langue:

english

Fichier:

PDF, 4.34 MB

english, 2019

14

Judgement of critical state of water film rupture on corrugated plate wall based on SIFT feature selection algorithm and SVM classification method

Wang, Bo, Tian, Ruifeng

Journal:

Nuclear Engineering and Design

Année:

2019

Langue:

english

Fichier:

PDF, 4.08 MB

english, 2019

15

Two-fluid equation for two-phase flow considering change in volume porosity

Lee, Jong Hyuk, Kim, Byoung Jae, Lee, Seung Wook, Kim, Kyung Doo

Journal:

Nuclear Engineering and Design

Année:

2019

Langue:

english

Fichier:

PDF, 2.60 MB

english, 2019

16

Thermal design optimization of passive cooling capability in a dry-storage system by adding wall undulations or semi-circular fins

Remache, Amel, Addad, Yacine, Sabeur-Bendehina, Amina, Ouadha, Ahmed

Journal:

Nuclear Engineering and Design

Année:

2019

Langue:

english

Fichier:

PDF, 1.02 MB

english, 2019

17

Sensitivity analysis for the distribution of maximum responses by seismic isolation system parameters using the stochastic response database

Eem, Seunghyun, Kim, Jung Han

Journal:

Nuclear Engineering and Design

Année:

2019

Langue:

english

Fichier:

PDF, 1.86 MB

english, 2019

18

Two-fluid equation for two-phase flow considering change in volume porosity

Lee, Jong Hyuk, Kim, Byoung Jae, Lee, Seung Wook, Kim, Kyung Doo

Journal:

Nuclear Engineering and Design

Année:

2019

Fichier:

PDF, 2.60 MB

2019

19

Thermal design optimization of passive cooling capability in a dry-storage system by adding wall undulations or semi-circular fins

Remache, Amel, Addad, Yacine, Sabeur-Bendehina, Amina, Ouadha, Ahmed

Journal:

Nuclear Engineering and Design

Année:

2019

Fichier:

PDF, 1.02 MB

2019

20

Sensitivity analysis for the distribution of maximum responses by seismic isolation system parameters using the stochastic response database

Eem, Seunghyun, Kim, Jung Han

Journal:

Nuclear Engineering and Design

Année:

2019

Fichier:

PDF, 1.86 MB

2019