Open Science Research Excellence

ICNEST 2019 : International Conference on Nuclear Energy Science and Technology

Zurich, Switzerland
July 29 - 30, 2019

Conference Code: 19CH07ICNEST

Conference Proceedings

All submitted conference papers will be blind peer reviewed by three competent reviewers. The peer-reviewed conference proceedings are indexed in the Open Science Index, Google Scholar, Semantic Scholar, Zenedo, OpenAIRE, BASE, WorldCAT, Sherpa/RoMEO, and other index databases. Impact Factor Indicators.

Special Journal Issues

ICNEST 2019 has teamed up with the Special Journal Issue on Nuclear Energy Science and Technology. A number of selected high-impact full text papers will also be considered for the special journal issues. All submitted papers will have the opportunity to be considered for this Special Journal Issue. The paper selection will be carried out during the peer review process as well as at the conference presentation stage. Submitted papers must not be under consideration by any other journal or publication. The final decision for paper selection will be made based on peer review reports by the Guest Editors and the Editor-in-Chief jointly. Selected full-text papers will be published online free of charge.

Conference Sponsor and Exhibitor Opportunities

The Conference offers the opportunity to become a conference sponsor or exhibitor. To participate as a sponsor or exhibitor, please download and complete the Conference Sponsorship Request Form.

Important Dates

Abstracts/Full-Text Paper Submission Deadline   February 28, 2019
Notification of Acceptance/Rejection   March 14, 2019
Final Paper (Camera Ready) Submission & Early Bird Registration Deadline   June 29, 2019
Conference Dates   July 29 - 30, 2019

Important Notes

Please ensure your submission meets the conference's strict guidelines for accepting scholarly papers. Downloadable versions of the check list for Full-Text Papers and Abstract Papers.

Please refer to the Paper Submission GUIDE before submitting your paper.

Selected Conference Papers

1) The Establishment of Probabilistic Risk Assessment Analysis Methodology for Dry Storage Concrete Casks Using SAPHIRE 8
J. R. Wang, W. Y. Cheng, J. S. Yeh, S. W. Chen, Y. M. Ferng, J. H. Yang, W. S. Hsu, C. Shih
2) Using TRACE, PARCS, and SNAP Codes to Analyze the Load Rejection Transient of ABWR
J. R. Wang, H. C. Chang, A. L. Ho, J. H. Yang, S. W. Chen, C. Shih
3) Uncertainty Analysis of ROSA/LSTF Test on Pressurized Water Reactor Cold Leg Small-Break Loss-of-Coolant Accident without Scram
Takeshi Takeda
4) Analysis of Possible Causes of Fukushima Disaster
Abid Hossain Khan, Syam Hasan, M. A. R. Sarkar
5) Implementation of Quantum Rotation Gates Using Controlled Non-Adiabatic Evolutions
Abdelrahman A. H. Abdelrahim, Gharib Subhi Mahmoud, Sherzod Turaev, Azeddine Messikh
6) Design Optimization of the Primary Containment Building of a Pressurized Water Reactor
M. Hossain, A. H. Khan, M. A. R. Sarkar
7) The Concentration Analysis of CO2 Using ALOHA Code for Kuosheng Nuclear Power Plant
W. S. Hsu, Y. Chiang, H. C. Chen, J. R. Wang, S. W. Chen, J. H. Yang, C. Shih
8) Radiative Reactions Analysis at the Range of Astrophysical Energies
A. Amar
9) Effect of Modeling of Hydraulic Form Loss Coefficient to Break on Emergency Core Coolant Bypass
Young S. Bang, Dong H. Yoon, Seung H. Yoo
10) CFD Simulation for Flow Behavior in Boiling Water Reactor Vessel and Upper Pool under Decommissioning Condition
Y. T. Ku, S. W. Chen, J. R. Wang, C. Shih, Y. F. Chang
11) An Authentication Protocol for Quantum Enabled Mobile Devices
Natarajan Venkatachalam, Subrahmanya V. R. K. Rao, Vijay Karthikeyan Dhandapani, Swaminathan Saravanavel
12) The Main Steamline Break Transient Analysis for Advanced Boiling Water Reactor Using TRACE, PARCS, and SNAP Codes
H. C. Chang, J. R. Wang, A. L. Ho, S. W. Chen, J. H. Yang, C. Shih, L. C. Wang
13) Using RASCAL Code to Analyze the Postulated UF6 Fire Accident
J. R. Wang, Y. Chiang, W. S. Hsu, S. H. Chen, J. H. Yang, S. W. Chen, C. Shih, Y. F. Chang, Y. H. Huang, B. R. Shen
14) Using TRACE and SNAP Codes to Establish the Model of Maanshan PWR for SBO Accident
B. R. Shen, J. R. Wang, J. H. Yang, S. W. Chen, C. Shih, Y. Chiang, Y. F. Chang, Y. H. Huang
15) Thermal Hydraulic Analysis of the IAEA 10MW Benchmark Reactor under Normal Operating Condition
Hamed Djalal

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