Open Science Research Excellence

ICQMS 2025 : International Conference on Quantum Materials and Structures

Zurich, Switzerland
July 29 - 30, 2025

Conference Code: 25CH07ICQMS

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

ICQMS 2025 has teamed up with the Special Journal Issue on Quantum Materials and Structures. 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 13, 2024
Notification of Acceptance/Rejection   February 27, 2024
Final Paper (Camera Ready) Submission & Early Bird Registration Deadline   June 29, 2025
Conference Dates   July 29 - 30, 2025

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) ROSA/LSTF Separate Effect Test on Natural Circulation under High Core Power Condition of Pressurized Water Reactor
Takeshi Takeda
2) ROSA/LSTF Test on Pressurized Water Reactor Steam Generator Tube Rupture Accident Induced by Main Steam Line Break with Recovery Actions
Takeshi Takeda
3) Study of Proton-9,11Li Elastic Scattering at 60~75 MeV/Nucleon
Arafa A. Alholaisi, Jamal H. Madani, M. A. Alvi
4) Effects of Level Densities and Those of a-Parameter in the Framework of Preequilibrium Model for 63,65Cu(n,xp) Reactions in Neutrons at 9 to 15 MeV
L. Yettou
5) Solitons and Universes with Acceleration Driven by Bulk Particles
A. C. Amaro de Faria Jr, A. M. Canone
6) 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
7) 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
8) Waste Management in a Hot Laboratory of Japan Atomic Energy Agency – 2: Condensation and Solidification Experiments on Liquid Waste
Sou Watanabe, Hiromichi Ogi, Atsuhiro Shibata, Kazunori Nomura
9) Uncertainty Analysis of ROSA/LSTF Test on Pressurized Water Reactor Cold Leg Small-Break Loss-of-Coolant Accident without Scram
Takeshi Takeda
10) Waste Management in a Hot Laboratory of Japan Atomic Energy Agency – 3: Volume Reduction and Stabilization of Solid Waste
Masaumi Nakahara, Sou Watanabe, Hiromichi Ogi, Atsuhiro Shibata, Kazunori Nomura
11) Waste Management in a Hot Laboratory of Japan Atomic Energy Agency – 1: Overview and Activities in Chemical Processing Facility
Kazunori Nomura, Hiromichi Ogi, Masaumi Nakahara, Sou Watanabe, Atsuhiro Shibata
12) Effect of Pre-Plasma Potential on Laser Ion Acceleration
Djemai Bara, Mohamed Faouzi Mahboub, Djamila Bennaceur-Doumaz
13) Assessment and Uncertainty Analysis of ROSA/LSTF Test on Pressurized Water Reactor 1.9% Vessel Upper Head Small-Break Loss-of-Coolant Accident
Takeshi Takeda
14) Study of Temperature Distribution in Coolant Channel of Nuclear Power with Fuel Cylinder Element Using Fluent Software
Elham Zamiri
15) Comparison of Two-Phase Critical Flow Models for Estimation of Leak Flow Rate through Cracks
Tadashi Watanabe, Jinya Katsuyama, Akihiro Mano

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