Some Novel on-Power Refuelling Features of Candu Stations.
Read Online
Share

Some Novel on-Power Refuelling Features of Candu Stations. by Atomic Energy of Canada Limited.

  • 49 Want to read
  • ·
  • 1 Currently reading

Published by s.n in S.l .
Written in English


Book details:

Edition Notes

1

SeriesAtomic Energy of Canada Limited. AECL -- 5387
ContributionsErwin, D., Watson, J.F., Pendlebury, B.
ID Numbers
Open LibraryOL21970866M

Download Some Novel on-Power Refuelling Features of Candu Stations.

PDF EPUB FB2 MOBI RTF

  In general, the refuelling calculation of the CANDU reactor is carried out every three days. It is necessary that the fuel management calculation should be finished within 2 or 3 h. The selection of channels for refuelling is a challenging task for the fuelling engineer at a CANDU by: ♦The CANDU on-power refuelling capability also means that long-term reactivity control can be achieved by an appropriate rate of fuel replacement. ♦Therefore, excess core-reactivity requirements are very small: ♦Current CANDU reactors use natural-uranium fuel, and the lattice has much smaller excess reactivity than enriched-fuel lattices. CANDU On-Power Refuelling Leads to: Constant global power shape, with localized ripples as channels are refuelled and go through their burnup cycle Constant in-core burnup Constant shutdown-system effectiveness Possibility of on-power removal of failed fuel, and therefore clean HTS. January Refuelling & Excess Core Reactivity. January. CANDU PHWRs use horizontal fuel channels arranged in a square lattice grid. The Fuelling Machine gains access to the fuel channels by means of a bridge structure supported by columns.

downs. The capability for on-power refuelling means that excess reactivity requirements are at a minimum: only a few milli-k are necessary for continuous and short-term reactivity control. This leads to excellent neutron economy and low fuelling costs. The primary objective of CANDU in-core fuel management is to determine fuel-loading and fuel-.   Refueling procedure for CANDU ACR reactors. Top 5 Weird WW2 German Prototypes That Actually Flew - Duration: The Iron Armenian aka . A report titled: CANDU STUDY AND REVIEW summarizes CANDU reactor features. Eight early CANDU reactors at Pickering, just east of Toronto, Ontario built during the early s. Total reactor capacity was about GWe in 8 units. The Bruce B Nuclear Generating Station on Lake Huron near Kincardin. The CANDU (Canada Deuterium Uranium) is a Canadian pressurized heavy-water reactor design used to generate electric power. The acronym refers to its deuterium oxide (heavy water) moderator and its use of (originally, natural) uranium fuel. CANDU reactors were first developed in the late s and s by a partnership between Atomic Energy of Canada Limited (AECL), the Hydro-Electric Power.

”The Essential CANDU” meets the long-standing need for a peer-reviewed textbook on the CANDU nuclear power technology, suitable for senior undergraduate and graduate students, educators, trainers and working professionals. It enables those new to CANDU to learn about CANDU as an overall system and to pursue specialized topics in depth. The on-power refuelling system of a CANDU uses two remotely operated fuelling machines, one at each end of the channel. During refuelling, the machines operate in pairs, locking onto opposite ends of the same channel. One machine inserts new-fuel bundles into the channel, while the other accepts the same number of discharged bundles.   On-power refueling and time-average model. To characterize the CANDU on-power refueling process, we will use a strategy that is divided in 2 components. The axial strategy that represents the number n s of fresh fuel bundles loaded in a channel at once (see Fig. 1) controls the flux shape along the core axis. Here, we consider a constant. The supply of steam from CANDU reactors for heavy water production / by R. F. S. Robertson. QC A75 NO Proceedings of the specialists' meeting on in-core instrumentation and failed fuel detection and location / convened by the IAEA Working Group on Nuclear Power Plant Control and Instrumentation ; edited by A. Pearson, G. F. Lynch, J. J.