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Volume 307

Nuclear Engineering and Design

Volume 307

1

Stress corrosion cracking behavior of annealed and cold worked 316L stainless steel in supercritical water

Sáez-Maderuelo, A., Gómez-Briceño, D.

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 2.73 MB

english, 2016

2

Molybdenum-99-producing 37-element fuel bundle neutronically and thermal-hydraulically equivalent to a standard CANDU fuel bundle

Nichita, E., Haroon, J.

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 1.48 MB

english, 2016

3

Development of digital device based work verification system for cooperation between main control room operators and field workers in nuclear power plants

Lee, Seung Min, Lee, Hyun Chul, Ha, Jun Su, Seong, Poong Hyun

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 1.60 MB

english, 2016

4

PHEBUS FPT-1 simulation by using MELCOR and primary blockage model exploration

Wang, Jun, Wang, Chen, Corradini, Michael L., Haskin, Troy, Tian, Wenxi, Su, Guanghui, Qiu, Suizheng

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 3.53 MB

english, 2016

5

Assessment calculation of MARS-LMR using EBR-II SHRT-45R

Choi, C., Ha, K.S.

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 8.82 MB

english, 2016

6

Flow regime, void fraction and interfacial area transport and characteristics of co-current downward two-phase flow

Lokanathan, Manojkumar, Hibiki, Takashi

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 3.86 MB

english, 2016

7

Modeling analyses of two-phase flow instabilities for straight and helical tubes in nuclear power plants

Dong, Ruiting, Niu, Fenglei, Zhou, Yuan, Yu, Yu, Guo, Zhangpeng

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 3.58 MB

english, 2016

8

3D modeling of missing pellet surface defects in BWR fuel

Spencer, B.W., Williamson, R.L., Stafford, D.S., Novascone, S.R., Hales, J.D., Pastore, G.

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 4.81 MB

english, 2016

9

Analysis of loss of offsite power events reported in nuclear power plants

Volkanovski, Andrija, Ballesteros Avila, Antonio, Peinador Veira, Miguel, Kančev, Duško, Maqua, Michael, Stephan, Jean-Luc

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 3.83 MB

english, 2016

10

Reduction on high level radioactive waste volume and geological repository footprint with high burn-up and high thermal efficiency of HTGR

Fukaya, Yuji, Nishihara, Tetsuo

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 981 KB

english, 2016

11

AP1000 station blackout study with and without depressurization using RELAP5/SCDAPSIM

Trivedi, A.K., Allison, C., Khanna, A., Munshi, P.

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 2.20 MB

english, 2016

12

Crane system with remote actuation mechanism for use in argon compartment in ACPF hot cell

Lee, Jong Kwang, Park, Byung-Suk, Yu, Seung-Nam, Kim, Kiho, Cho, Il-je

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 4.35 MB

english, 2016

13

Study on structural failure of RPV with geometric discontinuity under severe accident

Mao, J.F., Zhu, J.W., Bao, S.Y., Luo, L.J., Gao, Z.L.

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 4.41 MB

english, 2016

14

Rupture behaviour of nuclear fuel cladding during loss-of-coolant accident

Suman, Siddharth, Khan, Mohd. Kaleem, Pathak, Manabendra, Singh, R.N., Chakravartty, J.K.

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 1.78 MB

english, 2016

15

Validation and application of the system code ATHLET-CD for BWR severe accident analyses

Di Marcello, Valentino, Imke, Uwe, Sanchez, Victor

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 6.47 MB

english, 2016

16

Heavy metal oxide glasses as gamma rays shielding material

Kaur, Preet, Singh, Devinder, Singh, Tejbir

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 1.07 MB

english, 2016

17

Seismic risk control of nuclear power plants using seismic protection systems in stable continental regions: The UK case

Medel-Vera, Carlos, Ji, Tianjian

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 2.53 MB

english, 2016

18

Impact of fuel thermal conductivity degradation on Doppler feedback during rod ejection accident

Yilmaz, Mine O., Avramova, Maria N., Andersen, Jens G.M.

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 3.92 MB

english, 2016

19

OECD/NEA Sandia Fuel Project phase I: Benchmark of the ignition testing

Adorni, Martina, Herranz, Luis E., Hollands, Thorsten, Ahn, Kwang-II, Bals, Christine, D'Auria, Francesco, Horvath, Gabor L., Jaeckel, Bernd S., Kim, Han-Chul, Lee, Jung-Jae, Ogino, Masao, Techy, Zsol

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 3.58 MB

english, 2016

20

FLiNaK compatibility studies with Inconel 600 and silicon carbide

Yoder, Graydon L., Heatherly, Dennis, Wilson, Dane, Caja, Mario

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 5.99 MB

english, 2016

21

Improving safety margin of LWRs by rethinking the emergency core cooling system criteria and safety system capacity

Lee, Youho, Kim, Bokyung, NO, Hee Cheon

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 2.46 MB

english, 2016

22

Validation of system codes RELAP5 and SPECTRA for natural convection boiling in narrow channels

Stempniewicz, M.M., Slootman, M.L.F., Wiersema, H.T.

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 6.13 MB

english, 2016

23

Design and preliminary testing of a Bottom-Mounted Second Shutdown Drive Mechanism for the KJRR

Kim, Sanghaun, Lee, Jin Haeng, Yoo, Yeon-Sik, Cho, Yeong-Garp, Lee, Hyokwang, Sun, Jongoh, Ryu, Jeong Soo

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 2.05 MB

english, 2016

24

Sensitivity of stresses in TRISO-coated fuel particles to the coating layer properties

Li, Rong, Liu, Bing, Tang, Chunhe

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 3.95 MB

english, 2016

25

Thermal-hydraulic analysis of the improved TOPAZ-II power system using a heat pipe radiator

Zhang, Wenwen, Zhang, Dalin, Tian, Wenxi, Qiu, Suizheng, Su, G.H.

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 8.08 MB

english, 2016

26

Actinide-only and full burn-up credit in criticality assessment of RBMK-1500 spent nuclear fuel storage cask using axial burn-up profile

Barkauskas, V., Plukiene, R., Plukis, A.

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 892 KB

english, 2016

27

Leveraging comprehensive baseline datasets to quantify property variability in nuclear-grade graphites

Carroll, Mark C., Windes, William E., Rohrbaugh, David T., Strizak, Joseph P., Burchell, Timothy D.

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 2.77 MB

english, 2016

28

Pebble bed reactor fuel cycle optimization using particle swarm algorithm

Tavron, Barak, Shwageraus, Eugene

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 871 KB

english, 2016

29

Bayesian nonparametric analysis of crack growth rates in irradiated austenitic stainless steels in simulated BWR environments

Chimi, Yasuhiro, Takamizawa, Hisashi, Kasahara, Shigeki, Iwata, Keiko, Nishiyama, Yutaka

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 519 KB

english, 2016

30

Numerical solution of heat transfer process in a prismatic VHTR core accompanying bypass and cross flows

Wang, Li, Liu, Qiusheng, Fukuda, Katsuya

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 2.76 MB

english, 2016

31

Preliminary study to improve the performance of SCWR-M during loss-of-flow accident

Liu, X.J., Sun, C., Wang, Z.D., Chai, X., Xiong, J.B., Yang, Y.H., Cheng, X.

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 2.48 MB

english, 2016

32

Root cause study on hydrogen generation and explosion through radiation-induced electrolysis in the Fukushima Daiichi accident

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 1.79 MB

english, 2016

33

Development of the loss coefficient correlation for cross flow between graphite fuel blocks in the core of prismatic very high temperature reactor-PMR200

Lee, Jeong-Hun, Cho, Hyoung-Kyu, Park, Goon-Cherl

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 4.17 MB

english, 2016

34

Autonomous Reactivity Control (ARC) — Principles, geometry and design process

Qvist, Staffan A., Hellesen, Carl, Thiele, Roman, Dubberley, Allen E., Gradecka, Malwina, Greenspan, Ehud

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 4.59 MB

english, 2016

35

New strategies for quantifying and propagating nuclear data uncertainty in CUSA

Zhao, Qiang, Zhang, Chunyan, Hao, Chen, Li, Fu, Wang, Dongyong, Yu, Yan

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 4.16 MB

english, 2016