Research on Material Irradiation in HANARO

Abstract

HANARO (High-Flux Advanced Neutron Application Reactor) is a 30MWth multi-purpose research reactor generating a very high neutron flux for scientific and technical applications. Since its initial criticality in Feb. 1995, it has worked as a national neutron source for neutron beam research, RI production and related research, material and fuel irradiation research, and neutron transmutation doping. The installation of a cold neutron source and related beam instrument makes HANARO serve as a regional source for beam research as well. As Korea is developing nuclear power systems and fuels, irradiation research is a main utilization subject in HANARO, and irradiation facilities have been actively utilized for various nuclear fuel and material irradiation tests requested by users from research institutes, universities, and industries. Most of the irradiation tests were related to the R & D relevant to the ageing management and safety evaluation of the present nuclear power reactors. Korea is conducting R & D programs relevant to new nuclear systems including a research reactor, System-integrated Modular Advanced Reactor (SMART), and future nuclear systems such as a very high temperature reactor system (VHTR) and sodium cooled fast reactor system (SFR). To effectively support the R&D for new nuclear systems, advanced irradiation technologies such as high-temperature irradiation, instrumentation, and long-term irradiation are being developed. In addition, research on the irradiation characteristics of super-conductor materials and new chemical materials is being conducted as a part of fundamental research.

Share and Cite:

Cho, M. , Choo, K. , Yang, S. and Park, S. (2014) Research on Material Irradiation in HANARO. Journal of Applied Mathematics and Physics, 2, 855-861. doi: 10.4236/jamp.2014.29096.

Conflicts of Interest

The authors declare no conflicts of interest.

References

[1] Park, J.Y. (2009) Possibility of Fusion Applications of Current Materials R&D for GEN-IV Nuclear Energy System in KAERI. Korea-Japan Blanket Workshop.
[2] Yoon, J.H., et al. (2014) Characteristics of Domestic Reactor Pressure Vessel Steel after High-Dose Neutron Irradiation. Proceeding of HANARO Symposium.
[3] Lee, Y.M., et al. (2014) A Study on the Irradiated Strength and Stress Evaluation of nuclear Graphite Material. Nuclear Engineering and Design, 269, 193-199.
[4] William, K., et al. (2013) A Review of the Effects of Radiation on Microstructure and Properties of Concrete Used in Nuclear Power Plants. US NRC, NUREG/CR-7171.
[5] Hofman, G.L., et al. (2003) Proceeding of the 2003 RERTR International Meeting, Chicago, 5-10 October 2003.
[6] Jung, H.S., et al. (2014) Microwave Losses of Undoped n-Type Silicon and Undoped 4H-SiC Single Crystals at Cryogenic Temperatures. Electronic Materials Letters, 1-9.

Copyright © 2024 by authors and Scientific Research Publishing Inc.

Creative Commons License

This work and the related PDF file are licensed under a Creative Commons Attribution 4.0 International License.