• Proceedings of the Optical Society of Korea Conference
• /
• 2008.07a
• /
• pp.155-156
• /
• 2008

• Proceedings of the Korean Nuclear Society Conference
• /
• 2005.05a
• /
• pp.401-402
• /
• 2005

• Proceedings of the Korea Society for Energy Engineering kosee Conference
• /
• 2006.05a
• /
• pp.426-431
• /
• 2006

• Journal of Radiation Industry
• /
• v.6 no.3
• /
• pp.199-204
• /
• 2012

• 한국전기화학회:학술대회논문집
• /
• 2002.07a
• /
• pp.241-244
• /
• 2002

• Polymer Science and Technology
• /
• v.18 no.3
• /
• pp.253-258
• /
• 2007

• Safe Food
• /
• v.8 no.3
• /
• pp.3-11
• /
• 2013

• Nuclear Engineering and Technology
• /
• v.55 no.8
• /
• pp.2723-2733
• /
• 2023

Transuranic nuclides (such as ²³⁸Pu, ²⁵²Cf, ²⁴⁹Bk, etc.) have a wide range of application in industry, medicine, agriculture, and other fields. However, due to the complex conversion chain and remarkable fission losses in the process of transuranic nuclides production, the generation amounts are extremely low. High flux reactor with high neutron flux and flexible irradiation channels, is regarded as the promising candidate for producing transuranic nuclides. It is of great significance to increase the conversion ratio of transuranic nuclides, resulting in higher efficiency and better economy. In this paper, we perform an optimization design evaluation of producing transuranic nuclides in high flux reactor, which includes optimization design of irradiation target and influence study of reactor core loading. It is demonstrated that the production rate increases with appropriately determined target material and target structure. The target loading scheme in the irradiation channel also has a significant influence on the production of transuranic nuclides.

• Nuclear Engineering and Technology
• /
• v.56 no.5
• /
• pp.1679-1686
• /
• 2024

Graphite material plays an important role in nuclear reactors especially the high-temperature gas-cooled reactors (HTGRs) by its outstanding comprehensive nuclear properties. The structural integrity of graphite pebble fuel elements is the first barrier to core safety under any circumstances. The correct knowledge of the stiffness coefficient of the graphite pebble fuel element inside the reactor's core is significant to ensure the valid design and inherent safety. In this research, a vertical extrusion device was set up to measure the stiffness coefficient of the graphite pebble fuel element by the Institute of Nuclear and New Energy Technology (INET) of Tsinghua University in China. The stiffness coefficient equations of graphite pebble fuel elements at different temperatures are given (in a helium atmosphere). The result first provides the data on the high-temperature stiffness coefficient of pebbles in helium gas. The result will be helpful for the engineering safety analysis of pebble-bed nuclear reactors.

• Journal of the Optical Society of Korea
• /
• v.13 no.1
• /
• pp.37-41
• /
• 2009

We observe the proton signals produced by laser interaction with thin-foil targets of polyimide and of copper. We change the thickness of the polyimide target to $7.5{\mu}m$, $12.5{\mu}m$, and $50{\mu}m$. High-energy protons with the maximum energy of ${\sim}2.3\;MeV$ from $7.5{\mu}m$ thick polyimide are observed. This proton beam with the maximum energy of multi-MeV has various applications such as a proton shadowgraphy.