Background and Vision

• Nuclear power produces about 10% of global electricity, playing a vital role in reducing CO2 emissions and supporting long-term energy strategies in developed countries.

• The industry's future depends on operational safety and fuel efficiency.

• Computational simulation is essential for reactor design, safety analysis, and deploying advanced systems.

• This research direction is suitable for Vietnam: reasonable cost, not constrained by domestic manufacturing technology, direct access to core scientific problems and advanced global technologies.

Research Objectives

• Study advanced technologies: Focus on the physics of new-generation reactors (Gen IV), enhanced intrinsic safety, new fuel and core designs.

• Support the national nuclear program:

  • • Dalat Reactor (DNRR): Research reactor physics and nuclear data, utilize operational data, and collaborate with Dalat Nuclear Research Institute.

    • New multi-purpose research reactor: Prioritize research and design to support the planned 10 MW research reactor.

• Build group’s “brand”: Design and develop a Small Modular Reactor (SMR) concept to be the group’s signature technology.

• Safeguard national knowledge: Develop a strong research team with up-to-date expertise, especially given neighboring countries’ rapid nuclear expansion.

Capabilities and Methods

• Approach: Theoretical calculations and numerical simulations on HPC systems, using leading codes (MCNP6, Serpent, CASMO, COBRA-EN, SRAC2006, etc.).

• Collaboration with Dalat Nuclear Research Institute: Partners conduct experiments, while the group focuses on simulations, analysis, and data verification.

A further condensed version:

• Research and simulate nuclear reactor design: Suitable for Vietnam’s conditions, cost-effective, global technology access.

• Objectives: Improve safety and sustainability of new reactors, support national projects, develop SMR concept, ensure knowledge security.

• Methods: Numerical simulation, collaboration with Dalat Institute, use specialized software, leverage DNRR data.

Typical Achievements

The group's research capacity is affirmed through its publication record and funded projects. The group leader has published over 30 papers in reputable international journals (ISI/Scopus), is the chief editor of one monograph (VNU Press, 2023), and co-editor of another monograph (The IET Publisher, 2024).

The group has led and successfully participated in 5 NAFOSTED-funded projects directly related to this research area, demonstrating reliability and continuous high-level research capabilities:

• Research on reactor physics simulation (NAFOSTED 103.04-2014.79)

• Research on in-core fuel management of nuclear reactors using modern optimization methods (NAFOSTED 103.04-2016.30)

• Research on new fuel design and neutron noise analysis for nuclear reactor safety diagnostics (NAFOSTED 103.04-2017.20)

• Research on the physical aspects of advanced nuclear reactors (NAFOSTED 103.04-2020.06)

• Research on core physics of advanced nuclear reactors (NAFOSTED 103.04-2023.116)

Selected Scientific Publications:

1.     Van-Khanh Hoang, Giang T.T. Phan, Viet-Phu Tran, Thoi-Nam Chu, Huu-Tiep Nguyen, Haidang Phan, Van-Loat Bui, Hoai-Nam Tran*, “Core design optimization of a 200 MWt pressurized water SMR using evolutionary simulated annealing”, Nuclear Engineering and Design, 418, 112892, 2024.

2.     Thoi-Nam Chu, Giang T.T. Phan, Le Quang Linh Tran, Thi Hong Bui, Quang Binh Do, Duc-Tu Dau, Kien-Cuong Nguyen, Nhi-Dien Nguyen, Huu-Tiep Nguyen, Van-Khanh Hoang, Thanh Mai Vu, Hoai-Nam Tran*, “Sensitivity and uncertainty analysis of the first core of the DNRR using MCNP6 and new nuclear data libraries”, Nuclear Engineering and Design, 419, 112986, 2024.

3.     Tiep, N. H., Kim, J. S., Jeong, H. Y., Kim, K. D., Xuan-Mung, N., Tran, H. N.*, & Anh, N. N.* (2024), “Enhancement of Reflood Test Prediction by Integrating Machine Learning and Data Assimilation Technique”, International Journal of Energy Research, 2024, 6446405.

4.     Duc-Tu Dau, Nhi-Dien Nguyen, Ton-Nghiem Huynh, Quang-Huy Pham, Kien-Cuong Nguyen, Thoi-Nam Chu, Van-Khanh Hoang, Giang T.T. Phan, Huu-Tiep Nguyen, Thanh Mai Vu, Hoai-Nam Tran*, “Criticality and sensitivity/uncertainty analysis of the DNRR with LEU fuel sing MCNP6.3 and the latest data libraries” Nuclear Engineering and Design, 442 (2025) 114182. 

5.     Binh Do, Haidang Phan, Huu Tiep Nguyen, Thoi-Nam Chu, Van-Khanh Hoang, “Influence of problem characteristics on the optimal balance between population size and the number of generations in in-core fuel management using SHADE method”, Nuclear Engineering and Design, 443 (2025) 114258. 

6. Nguyen Huu Tiep, Hoai-Nam Tran* “Comment on “Evaluation of neutron radiation damage in the VVER-1200 reactor pressure vessel” by Louis et al.” Radiation Physics and Chemistry, 223 (2024) 111928.