[en] The Canada deuterium-uranium (CANDU)-3 reactor, with a net electrical output in the range of 450 MW, is the latest and smallest version of the very successful CANDU nuclear power system. A number of demanding design requirements were established at the outset of the CANDU-3 program. These included a 100-yr station design life, the ability to replace, modernize, or rehabilitate any aspect of the station within a 90-day outage, a 94% lifetime capacity factor, and a 30-month construction schedule from first concrete to in-service. To achieve these design requirements, CANDU Integrated Design (CANDID) Engineering and advanced construction methods were adopted. The use of advanced engineering and construction methods has contributed significantly to the CANDU-3 achieving design objectives. This enables CANDU-3 to be economically competitive with both larger nuclear and coal-fired generating plants

[en] The title of this paper highlights two key considerations which must be properly balanced through good management in the evolution of any engineering product. Excessive reliance on experience will lead to product stagnation; excessive reliance on innovation will often lead to an unsatisfactory product, at least in the first generation of this product. To illustrate this balancing process, the paper reviews CANDU evolution and experience and the balance between proveness and innovation achieved through management of the evolution process from early prototypes to today's large-scale commercial units. A forecast of continuing evolutionary directions is included

[en] This document compares the features CANDU and light-water PWR reactors. There is no essential difference between heavy water and light water pressurized water reactor power stations except in the reactor core design and in some aspects related to the heat transport system. The design of the CANDU reactor is simpler than other PWRs. CANDU power plants have consistently dominated world performance charts. The CANDU PWR has several inherent safety features lacking in other PWRs. Several options in new CANDU fuel cycles offer flexibility for the future

[en] The title of this paper highlights two key considerations which must be properly balanced through good management in the evolution of any engineering product. Excessive reliance on experience will lead to product stagnation; excessive reliance on innovation will often lead to an unsatisfactory product, at least in the first generation of this product. To illustrate this balancing process, the paper reviews CANDU evolution and experience and the balance between proveness and innovation achieved through management of the evolution process from early prototypes to today's large-scale commercial units. A forecast of continuing evolutionary directions is included

[en] CANDU is a relatively young technology which has demonstrated many achievements as an electrical power generation system. These achievements include an unsurpassed safety record, high annual and lifetime capacity factors, low electricity cost and a broad range of other performance strengths which together indicate that the CANDU technology is fundamentally sound. Known capabilities not yet fully exploited, such as advanced fuel cycle options, indicate that CANDU technology will continue to pay strong dividends on research, development and design investment. This provides a strong incentive for the improvement of CANDU on a continuing basis

[en] This invention relates to a moderator for a nuclear reactor and more specifically, to a composite moderator. A moderator is designed to slow down, or thermalize, neutrons which are released during nuclear reactions in the reactor fuel. Pure or almost pure materials like light water, heavy water, beryllium or graphite are used singly as moderators at present. All these materials, are used widely. Graphite has a good mechanical strength at high temperatures encountered in the nuclear core and therefore is used as both the moderator and core structural material. It also exhibits a low neutron-capture cross section and high neutron scattering cross section. However, graphite is susceptible to attach by carbon dioxide and/or oxygen where applicable, and releases stress energy under certain circumstances, although under normal operating conditions these reactions can be controlled. (author). 1 tab

[en] CAE, a private Canadian company specializing in full scope flight, industrial, and nuclear plant simulators, will provide a license to IAEA for a suite of nuclear power plant demonstrators. This suite will consist of CANDU, PWR and BWR demonstrators, and will operate on a 486 or higher level PC. The suite of demonstrators will be provided to IAEA at no cost to IAEA. The IAEA has agreed to make the CAE suite of nuclear power plant demonstrators available to all member states at no charge under a sub-license agreement, and to sponsor training courses that will provide basic training on the reactor types covered, and on the operation of the demonstrator suite, to all those who obtain the demonstrator suite. The suite of demonstrators will be available to the IAEA by March 1997. (author)

[en] The many and diverse technologies necessary for the design, construction licensing and operation of a nuclear power plant can be efficiently assimilated by a recipient country through an effective technology transfer program supported by the firm long term commitment of both the recipient country organizations and the supplier. AECL's experience with nuclear related technology transfer spans four decades and includes the construction and operation of CANDU plants in five countries and four continents. A sixth country will be added to this list with the start of construction of two CANDU 6 plants in China in early 1997. This background provides the basis for addressing the key factors in the successful transfer of nuclear technology, providing insights into the lessons learned and introducing a framework for success. This paper provides an overview of AECL experience relative to the important factors influencing technology transfer, and reviews specific country experiences. (author)

[en] AECL has completed the conceptual design of a small CANDU plant with an output, in the range of 300 MWth (called the CANDU 80), suitable for a variety of electrical and co-generation applications including desalination, oil sands oil extraction and processing, and the provision of electricity and heat to areas with low demand. This paper provides a brief overview of the CANDU 80, and discusses key features contributing to safety and operational margins

[en] Nuclear power has a history extending over more than 50 years; it has been pursued both for military power applications (primarily aircraft carrier and submarine propulsion) and for commercial power applications. Nuclear power has benefited from many hundreds of billions of dollars in research, development, design, construction, and operations expenditures, and has received substantial attention and support world-wide, having being implemented by most developed countries, including all of the G-7 countries, and several developing countries (for example, India, China, and Republic of Korea). In spite of this long history, massive development effort, and unprecedented financial commitment, nuclear power has failed to achieve commercial success, having captured less than 5% of the world's primary energy supply market. There are many factors contributing to the stagnation/decline of the commercial nuclear power business. These factors include: non competitive economics, lengthy construction schedules, large and demanding human resource requirements, safety concerns, proliferation concerns, waste management concerns, the high degree of government financial and political involvement necessary, and the incompatibility of the available nuclear power plant designs with most process heat applications due to their temperature limitations and/or large heat output. An examination of the obstacles to deployment of nuclear power plants of current design suggest a set of requirements for new nuclear power plants, which may overcome or circumvent these obstacles. These requirements include: inherent characteristics that will achieve reactor shutdown under any postulated accident condition; the removal of decay heat by natural and passive means; no safety dependence on operator actions and tolerant to operator error, and malicious or incompetent operator action; and, economic viability in relatively small unit sizes. Many innovative reactor technologies and concepts are under consideration around the world. Several of these innovative concepts are capable of satisfying many of the requirements identified. These include the High Temperature Gas Reactors (HTGRs), the Lead-cooled Integral Reactor (LEADIR), the Molten-Salt Reactor (MSR), the BREST fast reactor, and the accelerator driven Energy Amplifier. All of these designs have high temperature capability, (core outlet temperature in the range of 650^oC to 900^oC). This paper reviews the current obstacles to nuclear power deployment, proposes a comprehensive set of requirements for future nuclear power plants that incite serve to overcome the obstacles identified, and discusses five innovative reactor technologies/concepts that are capable of meeting most of the requirements identified. (author)