Excellence in Research and Innovation for Humanity

ICNWMDGD 2019 : 21st International Conference on Nuclear Waste Management and Deep Geological Disposal

Lisbon, Portugal
April 16 - 17, 2019

Conference Code: 19PT04ICNWMDGD

Conference Proceedings

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

Special Journal Issues

ICNWMDGD 2019 has teamed up with the Special Journal Issue on Nuclear Waste Management and Deep Geological Disposal. 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   October 26, 2018
Notification of Acceptance/Rejection   November 9, 2018
Final Paper (Camera Ready) Submission & Early Bird Registration Deadline   March 16, 2019
Conference Dates   April 16 - 17, 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) Analysis of Possible Causes of Fukushima Disaster
Abid Hossain Khan, Syam Hasan, M. A. R. Sarkar
2) Implementation of Quantum Rotation Gates Using Controlled Non-Adiabatic Evolutions
Abdelrahman A. H. Abdelrahim, Gharib Subhi Mahmoud, Sherzod Turaev, Azeddine Messikh
3) Design Optimization of the Primary Containment Building of a Pressurized Water Reactor
M. Hossain, A. H. Khan, M. A. R. Sarkar
4) 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
5) Radiative Reactions Analysis at the Range of Astrophysical Energies
A. Amar
6) Effect of Modeling of Hydraulic Form Loss Coefficient to Break on Emergency Core Coolant Bypass
Young S. Bang, Dong H. Yoon, Seung H. Yoo
7) 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
8) Steady State Natural Convection in Vertical Heated Rectangular Channel between Two Vertical Parallel MTR-Type Fuel Plates
Djalal Hamed
9) Thermal Hydraulic Analysis of the IAEA 10MW Benchmark Reactor under Normal Operating Condition
Hamed Djalal
10) Numerical Solution of Transient Natural Convection in Vertical Heated Rectangular Channel between Two Vertical Parallel MTR-Type Fuel Plates
Djalal Hamed
11) Using RASCAL and ALOHA Codes to Establish an Analysis Methodology for Hydrogen Fluoride Evaluation
J. R. Wang, Y. Chiang, W. S. Hsu, H. C. Chen, S. H. Chen, J. H. Yang, S. W. Chen, C. Shih
12) 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
13) 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
14) Degradation of Irradiated UO2 Fuel Thermal Conductivity Calculated by FRAPCON Model Due to Porosity Evolution at High Burn-Up
B. Roostaii, H. Kazeminejad, S. Khakshournia
15) Reduction of Plutonium Production in Heavy Water Research Reactor: A Feasibility Study through Neutronic Analysis Using MCNPX2.6 and CINDER90 Codes
H. Shamoradifar, B. Teimuri, P. Parvaresh, S. Mohammadi

Similar conferences about Nuclear and Quantum Engineering