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The Assembly and Test of Pressure Vessel for Irradiation

조사시험용 압력용기의 조립 및 시험

  • Published : 2009.02.01

Abstract

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 keep the functionality of the reactor coolant pressure boundary. The IVA is manufactured by local company and the functional test and verification were done through pressure drop, vibration, hydraulic and leakage tests. The brazing technique for the instrument lines has been checked for its functionality and performance. An IVA has been manufactured by local technique and have finally tested under high temperature and high pressure. The IVA and piping did not experience leakage, as we have checked the piping, flanges, assembly parts. We have obtained good data during the three cycle test which includes a pressure test, pressure and temperature cycling, and constant temperature.

Keywords

References

  1. Park, K.N., Lee, J.M., Lee, C.Y., Kim, H.R., Kim, Y.J. and Yoo, S.Y., 2005, "Manufacturing Design and Mock-up Fabrication of IPS Vessel Assembly," Journal of Korean Society of Mechanical Technology, Vol. 7, No. 2, pp. 29-33
  2. Korea Atomic Energy Research Institute and RWE NUKEM, 2006, "Manufacturing Specification for In-Pile Section," HAN-FL-310-DTR005
  3. ASME, "Brazing", Boiler and Pressure Vessel Code, Sec. IX, Part QB
  4. ASME, "Testing," Boiler and Pressure Vessel Code, Sec. III, Subsection NB-6000
  5. Korea Atomic Energy Research Institute, 2007, "Hanaro FTL Pre-operation Procedure - Test Procedure of IVA High Temperature High Pressure," HAN-FL-S-062-DO-K115
  6. Korea Atomic Energy Research Institute, 2001, "Construction & Commissioning Test Report of CEDM Test Facility," KAERI/TR-1764

Cited by

  1. Development of Induction Brazing System for Sealing Instrumentation Feedthrough Part of Nuclear Fuel Test Rig vol.37, pp.12, 2013, https://doi.org/10.3795/KSME-A.2013.37.12.1573