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The fuel string relocation effect - why the Bruce reactors were derated

Abstract

In the CANDU Safety Analysis process, a series of design basis accidents are chosen and analyzed to confirm safety system effectiveness. Of all the postulated accidents, the Large Break Loss of Coolant Accident (LBLOCA) - a postulated break in the Heat Transport System piping near a component that services a large number of fuel channels - sets the most demanding requirements on the speed and reactivity depth of the shutdown system devices - shutoff rods and liquid poison injection. While the event is extremely improbable, it is reanalyzed periodically and its consequences examined to ensure continued shutdown system effectiveness. In March 1993, an additional effect was identified: if the break occurred in the piping on the inlet side of the core, this would cause sudden movement of the fuel bundles (so-called fuel string relocation) in a large number of channels. In Ontario Hydro`s Bruce NGS A, Bruce NGS B and Darlington reactors, each channel is fuelled against the flow. In this situation, the relocation of the fuel string results in a sudden positive reactivity increase. This reactivity increase is in addition to the reactivity due to the core coolant voiding. The combined reactivity effect could lead to power pulses much  More>>
Authors:
Gold, M; Farooqui, M Z; Adebiyi, A S; Chu, R Y; Le, N T; Oliva, A F; [1]  Balog, G; Qu, T; DeBuda, P G [2] 
  1. Ontario Hydro, Toronto, ON (Canada)
  2. Ontario Hydro, Tiverton, ON (Canada). Bruce Nuclear Generating Station-A
Publication Date:
Dec 31, 1995
Product Type:
Conference
Report Number:
INIS-CA-0053; CONF-950623-
Reference Number:
SCA: 210400; PA: AIX-28:076170; EDB-97:143829; SN: 97001880576
Resource Relation:
Conference: 35. annual conference of the Canadian Nuclear Association and 16th annual conference of the Canadian Nuclear Society, Saskatoon (Canada), 4-7 Jun 1995; Other Information: PBD: 1995; Related Information: Is Part Of CNS proceedings of the 16. annual conference, volume I and II; Wight, A.L.; Loewer, R. [eds.]; PB: [2 v. ] p.
Subject:
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; BRUCE-1 REACTOR; REACTOR SAFETY; FUEL CHANNELS; REACTOR FUELING; BRUCE-5 REACTOR; DARLINGTON-1 REACTOR; FUEL ELEMENT CLUSTERS; FUEL MANAGEMENT; LOSS OF COOLANT; MODIFICATIONS; PRIMARY COOLANT CIRCUITS; TRANSIENTS
OSTI ID:
545994
Research Organizations:
Canadian Nuclear Society, Toronto, ON (Canada)
Country of Origin:
Canada
Language:
English
Other Identifying Numbers:
Other: ON: DE98603788; TRN: CA9700787076170
Availability:
INIS; OSTI as DE98603788
Submitting Site:
INIS
Size:
pp. [13]
Announcement Date:
Dec 10, 1997

Citation Formats

Gold, M, Farooqui, M Z, Adebiyi, A S, Chu, R Y, Le, N T, Oliva, A F, Balog, G, Qu, T, and DeBuda, P G. The fuel string relocation effect - why the Bruce reactors were derated. Canada: N. p., 1995. Web.
Gold, M, Farooqui, M Z, Adebiyi, A S, Chu, R Y, Le, N T, Oliva, A F, Balog, G, Qu, T, & DeBuda, P G. The fuel string relocation effect - why the Bruce reactors were derated. Canada.
Gold, M, Farooqui, M Z, Adebiyi, A S, Chu, R Y, Le, N T, Oliva, A F, Balog, G, Qu, T, and DeBuda, P G. 1995. "The fuel string relocation effect - why the Bruce reactors were derated." Canada.
@misc{etde_545994,
title = {The fuel string relocation effect - why the Bruce reactors were derated}
author = {Gold, M, Farooqui, M Z, Adebiyi, A S, Chu, R Y, Le, N T, Oliva, A F, Balog, G, Qu, T, and DeBuda, P G}
abstractNote = {In the CANDU Safety Analysis process, a series of design basis accidents are chosen and analyzed to confirm safety system effectiveness. Of all the postulated accidents, the Large Break Loss of Coolant Accident (LBLOCA) - a postulated break in the Heat Transport System piping near a component that services a large number of fuel channels - sets the most demanding requirements on the speed and reactivity depth of the shutdown system devices - shutoff rods and liquid poison injection. While the event is extremely improbable, it is reanalyzed periodically and its consequences examined to ensure continued shutdown system effectiveness. In March 1993, an additional effect was identified: if the break occurred in the piping on the inlet side of the core, this would cause sudden movement of the fuel bundles (so-called fuel string relocation) in a large number of channels. In Ontario Hydro`s Bruce NGS A, Bruce NGS B and Darlington reactors, each channel is fuelled against the flow. In this situation, the relocation of the fuel string results in a sudden positive reactivity increase. This reactivity increase is in addition to the reactivity due to the core coolant voiding. The combined reactivity effect could lead to power pulses much higher than those that would arise due to coolant voiding alone. To maintain safety margins in the event of such a postulated accident, the eight Bruce NGS A and Bruce NGS B units were initially derated to 60 percent power within 2 days of the identification and confirmation of this effect. This paper: describes the fuel string relocation phenomenon in detail; explains why the consequences differ at the various Ontario Hydro reactors; outlines the actions taken with respect to each of the Ontario Hydro reactors in the months following March 1993; describes the design solutions implemented to mitigate the problem and return the Bruce reactors to higher powers. 6 refs., 1 tab., 6 figs.}
place = {Canada}
year = {1995}
month = {Dec}
}