NSRR
NSRR is one of the research reactors referred to as the “TRIGA reactor,” and is the exclusive reactor for nuclear fuel safety research. Since its first criticality in June 1975, more than 3150 pulse operations and more than 1330 fuel irradiation experiments had been conducted. The experimental facilities were modified in 1989, and the operational and experimental capabilities were thereby greatly improved.
An outside view of the NSRR reactor building
A cutaway view of the NSRR reactor
An outline of NSRR
◎ Specifications of NSRR
| Reactor core | Effective height:. | Approximately 38 cm |
| Effective diameter: | Approximately.63 cm | |
| Moderator: | ZrH、H2O | |
| Fuel rods | Fuel: | U-ZrH（Uranium-Zirconium-hydride） |
| Enrichment: | 20% | |
| Cladding: | Stainless steel(SUS304) | |
| Shape / dimensions: | Φ3.57 cm × L 65 cm | |
| Number of rod: | 157 | |
| Maximum Inserted reactivity: | $4.7 | |
| Maximum reactor power: | ～23 GW | |
| Maximum Integrated power: | ～130 MW・s | |
◎ Link to NSRR homepage(in Japanese)
→ http://drrta.jaea.go.jp/2/23.htm