The Fuel Test Loop (FTL) which is capable of an irradiation testing under a similar operating condition to those of PWR (Pressurized Water Reactor) and CANDU (CANadian Deuterium Uranium reactor) nuclear power plants has been developed and installed in HANARO, KAERI (Korea Atomic Energy Research Institute). It consists of In-Pile Section (IPS) and Out-of Pile System (OPS). The IPS, which is located inside the pool is divided into 3-parts; the in-pool pipes, the IVA (IPS Vessel Assembly) and the support structures. The test fuel is loaded inside a double wall, inner pressure vessel and outer pressure vessel, to maintain the functionality of the reactor coolant pressure boundary. The functional test and verification of the IVA were done through pressure drop, vibration, hydraulic and helium leakage tests. The brazing technique for the instrument lines has been checked for its functionality and performance. An IVA has been manufactured by a local technique and has finally been tested under high temperature and high pressure. The IVA and piping did not experience leakage, as the piping, flanges, and assemblies have been fully checked. Good data was obtained during the three cycle test which included a pressure test, pressure and temperature cycling, and constant temperature. A new concept of IVA, as easy attaching and separating test fuel at IVA will be designed thereafter.
- Pressure Vessels and Piping Division
The Function Test for the Reliability Confirmation of High Temperature and High Pressure Vessel for Irradiation
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Park, K, Lee, J, Ahn, S, Wu, S, & Kim, Y. "The Function Test for the Reliability Confirmation of High Temperature and High Pressure Vessel for Irradiation." Proceedings of the ASME 2010 Pressure Vessels and Piping Division/K-PVP Conference. ASME 2010 Pressure Vessels and Piping Conference: Volume 7. Bellevue, Washington, USA. July 18–22, 2010. pp. 181-187. ASME. https://doi.org/10.1115/PVP2010-25388
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