Fuel and component handling in PFR and intentions for CDFR
Creators
- 1. UKAEA Dounreay Nuclear Power Development Establishment
- 2. Nuclear Power Co. (Risley) Ltd. (UK)
- 3. UKAEA Risley Nuclear Power Development Establishment
Description
The extensive operating experience with fuel and component handling in the Prototype Fast Reactor (PFR) is summarized, with emphasis on the fuel transfer system. The route for fuel sub-assemblies, including preparation in the new fuel cell, transfer to the storage rotor within the reactor vessel, transfer between rotor and core and the return to the irradiated fuel cave is described with details of experience so far. The cave was commissioned in 1977 and has received the first irradiated fuel from the reactor for examination. A large number of sub-assemblies has been handled between storage rotor and core without significant difficulty and the design rates of transfer have been achieved. The fuel charge machine must be loaded into the reactor for each refuelling operation. The design of a machine which can remain in the reactor during operation is being prepared, since experience indicates that the time for refuelling shutdowns can be substantially reduced. Considerable experience has been gained in the transfer of other components to, from and within the sodium circuits of PFR using bagging and flasking techniques. Large bags have been used extensively for components which are not radioactive, including sodium pumps and steam generator tube bundles. More recently the shielded flasks have been commissioned for primary circuit transfers. Based on the lessons learned during the early testing and subsequent operation of the PFR, the fuel handling system for the large Commercial Demonstration Fast Reactor (CDFR) has been designed. The proposed fuel route is described with emphasis on the transfer between the core and a fuel store located outside the primary containment. (author)
Additional details
Publishing Information
- Publisher
- IAEA.
- Imprint Place
- Vienna
- ISBN
- 92-0-050278-4
- Imprint Title
- Design, construction and operating experience of demonstration LMFBRs
- Series
- Proceedings series.
- Journal Page Range
- p. 425-433.
Conference
- Title
- International symposium on design, construction and operating experience of demonstration liquid metal fast breeder reactors.
- Dates
- 10 - 14 Apr 1978.
- Place
- Bologna, Italy.
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 11509081
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CONTAMINATION; FUEL ASSEMBLIES; FUEL ASSEMBLY DISMANTLING; FUEL ELEMENTS; FUEL MANAGEMENT; PFR REACTOR; REACTOR CHARGING MACHINES; REACTOR FUELING
- Descriptors DEC
- BREEDER REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; MANAGEMENT; NUCLEAR MATERIALS MANAGEMENT; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SODIUM COOLED REACTORS
Optional Information
- Secondary number(s)
- IAEA-SM--225/69.