A Next Generation Heavy Water Nuclear Reactor with Supercritical Water as Coolant
International Conference on the Future of Heavy Water Reactors - 2011 October 02-05


Presented at:
International Conference on the Future of Heavy Water Reactors
2011 October 02-05
Location:
Ottawa, Canada
Session Title:
Super-Critical Water-cooled Reactors

Authors:
Laurence K.H. Leung (Atomic Energy of Canada Limited)
M. Yetisir (Atomic Energy of Canada Limited)
William Diamond (Atomic Energy of Canada Limited)
D. Martin (Atomic Energy of Canada Limited)
Jeremy Pencer (Atomic Energy of Canada Limited)
Bronwyn Hyland (Atomic Energy of Canada Limited)
H. Hamilton (Atomic Energy of Canada Limited)
D. Guzonas (Atomic Energy of Canada Limited)
Romney Duffey (Atomic Energy of Canada Limited)
  

Abstract

The supercritical water (SCW) cooled nuclear reactor is one of six candidate reactor concepts selected by the Generation-IV International Forum (GIF) for meeting GIF design goals, which includes enhanced safety, resource sustainability, economic benefit and proliferation resistance [1]. As a member of GIF, Canada is developing a pressure-tube type SCW reactor, which has the potential to fulfill all major GIF goals. Employing the existing supercritical water technology used in coal plants on the balance-of-power systems, the Canadian SCWR design effort focuses mainly on the core configuration to generate supercritical water at the temperature of 625°C matching closely the existing high-pressure turbine design (thereby increasing the thermal efficiency by 40% as compared to the conventional nuclear power plants).

This paper presents the pre-conceptual design of a heavy-water moderated pressure-tube type SCWR, which has evolved from the well-established CANDU reactor. It describes the core configuration, advanced thorium fuel cycle, the high-efficiency fuel channel design, passive moderator cooling system, and fuel design. These key components facilitate the fulfillment of the GIF design goals.

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