Conceptual Design of a 10 MW Multipurpose Research Reactor Using VVR-KN Fuel

Abstract

The paper presents a conceptual design of a 10 MW multipurpose nuclear research reactor (MPRR) loaded with the low-enriched uranium (LEU) VVR-KN fuel type. Neutronics and burnup calculations have been performed using the REBUS-MCNP6 linkage system code and the ENDF/B-VII.0 data library. The core consists of 36 fuel assemblies: 27 standard fuel assemblies and 9 control fuel assemblies with the uranium density of 2.8 gU/cm3 and the 235U enrichment of 19.75 wt.%. The cycle length of the core is 86 effective full-power days with the excess reactivity of 9600 and 1039 pcm at the beginning of cycle and the end of cycle, respectively. The highest power rate and the highest discharged burnup of fuel assembly are 393.49 kW and 56.74% loss of 235U, respectively. Thermal hydraulics analysis has also been conducted using the PLTEMP4.2 code for evaluating the safety parameters at a steady state of the hottest channel. The maximum temperatures of coolant and fuel cladding are 66.0°C and 83.0°C, respectively. This value is lower than the design limit of 98°C for cladding temperature. Thermal fluxes at the vertical irradiation channels and the horizontal beam ports have been evaluated. The maximum thermal fluxes of 2.5 × 1014 and 8.9 ×1013 n·cm−2·s−1 are found at the neutron trap and the beryllium reflector, respectively.

Investigate the potential of using reactor anti-neutrinos for nuclear safeguards in Vietnam

“…Vietnam currently has only one small research nuclear reactor with a nominal power of 500 kW, the Dalat Nuclear Research Reactor (DNRR) [50], which has been operational for 60 years. DNRR has been used for neutron scattering, neutron activation analysis, material testing, medicine application, and biological science research, education, and training [51][52][53]. Since 2011, DNRR has been fully operating with the Low Enriched Uranium (LEU) fuel of 19.75% 235 U at 500 kW power.…”

“…However, due to its low power and facility limitations, this research reactor will be unable to meet the increasing demands of research and application in the future. In the near future, another 10 MW nuclear reactor for multipurpose research (MPRR) [51] is planned to be built. Aside from traditional applications, MPRR is being developed for advanced research and applications such as neutron transmutation doping of silicon and neutron scattering material science research.…”

Simulation of natural convection flow for vertical heated rod by using ANSYS/Fluent

“…Therefore, the convective natural flow of vertical is needed to for further application of nuclear reactor fuel rod. Nguyen et al [6] investigated the operational condition of a 10 MW research reactor with various system codes to verify this reactor's conceptual design. However, the detailed information on the flow and heat removal through a narrow gap of fuel elements still needs to be included.…”

Preparation of guidance on the appraisal of the environmental impact assessment report for the center for nuclear science and technology of Vietnam

“…Currently, Vietnam has only one research reactor -the Dalat NRR with a nominal capacity of 500 kW, whose main purpose is training, radioisotope production, neutron activation analysis, and basic research. During its operation, the Dalat NRR played a very important role in the development of Vietnam's nuclear infrastructure and produced a large number of products and services [3]. However, due to the limitation of the neutron flux level, the outdated design of the experimental facilities, and the aging of the reactor equipment, the research reactor cannot meet the growing needs of users.…”