Published 1978 | Version v1
Book

Fuel and component handling in PFR and intentions for CDFR

  • 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.