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Cw-03500-Conf-013 R0 Unrestricted 11th International Conference on CANDU Fuel Sheraton Fallsview Hotel and Conference Centre Niagara Falls, Ontario, Canada, 2010 October 17-20 SAFETY ASSESSMENT ON NUE FUEL BUNDLES FOR DEMONSTRATION IRRADIATION IN A CANDU REACTOR H.Z. Fan, Z. Li, N. Barkman, C. Cottrell, A. Ranger Atomic Energy of Canada Limited (AECL), Mississauga, Ontario, Canada ABSTRACT—The CANDUâ1 reactors have a unique fuel cycle capability that enables them to utilize alternative fuel options. One option currently being developed is Natural Uranium Equivalent (NUE) fuel. This fuel is not fabricated from natural uranium but from a mixture of depleted uranium and recycled uranium that follows the fundamental specifications for natural uranium (NU) fuel and mimics its performance. Recycling uranium from reprocessing facilities reintroduces the uranium into the fuel cycle and will improve the utilization rate of NU resources; ultimately improving the sustainability of fuel resources. The concept of using NUE is currently being implemented as a demonstration in the Qinshan CANDU units in China. The NUE fuel has been manufactured in China and utilized in a two-channel demonstration irradiation in one of the Qinshan CANDU units. A safety assessment has been performed which has concluded that there are no safety concerns or adverse implications of replacing NU fuel with NUE fuel for the two -channel demonstration irradiation. This paper is an overview of this safety assessment. 1. Introduction The CANDU reactors have a unique fuel cycle capability that enables them to utilize alternative fuel options. Recently, in 2010 March, the first-ever fuel bundle to directly use recovered uranium from light water reactors was successfully placed in the Qinshan CANDU Unit 1 Pressurized Heavy Water Reactor. Over the next six months, a total of 24 Natural Uranium Equivalent (NUE) fuel bundles will be inserted into two separate fuel channels for the demonstration irradiation. The NUE fuel is fabricated from a mixture of depleted uranium (DU) and recycled uranium (RU) that follows the fundamental specifications for natural uranium (NU) fuel and mimics its performance. Recycling uranium from reprocessing facilities reintroduces the uranium into the fuel cycle and will improve the utilization rate of NU resources; ultimately improving the sustainability of fuel resources. This commercial demonstration of NUE fuel is a first-of-a-kind advanced fuel collaborative effort for AECL and its Chinese partners: Third Qinshan Nuclear Power Company Limited, Nuclear Power Institute of China and China North Nuclear Fuel Corporation, and highlights the beginning of the engineering application of CANDU advanced fuel cycles. It establishes the ability of the CANDU reactor to utilize alternative fuel cycles and demonstrates the strong synergy between CANDU technology and light water reactor technology. The project was initiated in 2008 to explore the use of recovered uranium from light water reactors in a CANDU reactor and to prove that it is the simplest, most cost-effective and environmentally-friendly process to utilize alternative fuel sources. 1 CANDUÒ is a registered trademark of Atomic Energy of Canada Limited (AECL). Page 1 © Atomic Energy of Canada Limited, 2010 11th International Conference on CANDU Fuel Sheraton Fallsview Hotel and Conference Centre Niagara Falls, Ontario, Canada, 2010 October 17-20 As part of this work, a safety assessment was undertaken which has concluded that there are no safety concerns or adverse implications of replacing NU fuel with NUE fuel for the two-channel demonstration irradiation. This paper is an overview of this safety assessment. 2. Safety Assessment on NUE Fuel 2.1 Strong technical base for NUE fuel program The planned NUE fuel development and demonstration irradiation program is built on a strong technical base. Figure 1 CANDU Fuel Cycles AECL has been continually engaged in CANDU fuel cycle development (Figure 1), with many theoretical and experimental studies carried out over the years and several are in progress today. AECL’s experience in developing, processing, fabricating, irradiating, and examining (post irradiation) advanced fuels extends back to the 1950s in AECL’s first research reactors, and encompasses a variety of uranium and thorium oxides and fissile and fertile materials recovered from previously irradiated fuels, in some cases in combination with each other. All fuel used in CANDU reactors, beginning with the Nuclear Power Demonstration reactor in 1962, was first qualified in AECL research reactors. Fuel for the Advanced CANDU Reactor is currently being qualified in AECL’s National Research Universal (NRU) reactor. Low void reactivity fuel has been qualified in AECL’s research reactors and demonstrated in CANDU reactors by Bruce Power Corporation. As mentioned in Section 1, AECL has recently added another advanced fuel cycle, a natural uranium equivalent fuel, as a commercial entry point to use recycled uranium in CANDU reactors. It is economically attractive, technically simple and directly licensable for operating CANDUs. Recycling of the fissile and fertile components of spent fuel from light Page 2 © Atomic Energy of Canada Limited, 2010 11th International Conference on CANDU Fuel Sheraton Fallsview Hotel and Conference Centre Niagara Falls, Ontario, Canada, 2010 October 17-20 water reactors, and reusing them as fuel in CANDU reactors, increases the energy produced per unit mass of original mined ore compared to that extracted in a once-through nuclear fuel cycle. AECL’s wide range of experience in fabricating fuel pellets from a variety of radioactive and fissile materials like natural uranium, recycled uranium, Mixed Oxide (MOX), Direct Use of spent Pressurized water reactor fuel In CANDU (DUPIC), and thorium, is supplemented by extensive research reactor and power reactor irradiation and post irradiation examinations. This extensive experience has given AECL an in-depth understanding of the factors required to specify, design, and fabricate fuel pellets with the desired characteristics. This work has also allowed AECL to develop a considerable knowledge base of the requirements for managing radiation hazards associated with pellet fabrication. The use of RU has a worldwide history of more than thirty years. According to the International Atomic Energy Agency, RU has been successively used in over forty reactors in various countries such as, Belgium, France, Germany, and India. Many utilities, especially in Europe and Japan, are using Enriched RU (ERU) in light water reactors (LWRs). These utilities have had to address many safety issues in operational, radiation protection (radiation dose and shield ing), environmental, fuel fabrication, reactor control, fresh fuel storage, transient analysis, decay heat, waste management etc related to the use of ERU. Their experience has shown that the safety issues associated with ERU utilization are within the operating envelope of enriched natural uranium fuel. They concluded that neutronic differences are insignificant to have any impact on the neutronic compatibility and design. Due to enrichment requirements for LWRs, RU has to be over-enriched by levels as high as 4.5% to compensate for the presence of neutron absorbers. This step is not required for using RU in CANDU reactors. Instead, the RU is mixed with depleted uranium (DU) to form NUE fuel which is designed to be neutronically equivalent to NU fuel. The CANDU neutron spectrum is much softer than that in a light water reactor. This characteristic requires that the 235U isotopic content of the NUE fuel needs to be only slightly higher (a much lower over enrichment of about 0.01~0.02 wt% for CANDU reactor use) than that of NU to compensate for the presence of neutron absorbers in RU, which are not present in NU. The recycled uranium (RU) and depleted uranium (DU), depending on their initial 235U content, can be blended in various ratios to ensure that the final product closely resembles NU fuel and has minimal reactor safety and licensing barriers for deployment in the CANDU reactor. AECL has extensive experience in processing and fabricating alternative fuels and irradiating them in heavy water moderated, fuel channel research and power reactors. This experience has been used to implement the NUE fuel development and demonstration program. 2.2 Current licensing basis and NUE fuel safety assessment Qinshan CANDU 6 reactors are designed by AECL and licensed in China based on Canadian safety requirements and Chinese regulatory requirements. The final safety analysis report (FSAR) for the Qinshan CANDU reactors forms the current licensing basis using NU fuel. The Page 3 © Atomic Energy of Canada Limited, 2010 11th International Conference on CANDU Fuel Sheraton Fallsview Hotel and Conference Centre Niagara Falls, Ontario, Canada, 2010 October 17-20 CNSC requirements reflected in several AECB* regulatory documents (References [1] and [6]) are considered as the acceptable limits for the analysis results. Any plant state requirements from these documents have been incorporated into the acceptance criteria for events analyzed in the Qinshan CANDU FSAR. The acceptable limits for the results are judged, based on AECB requirements and appropriate analysis targets that apply to public dose, reactor shutdown, fuel and fuel channel integrity, calandria structural integrity, containment structural integrity, and heat transport system overpressure protection. Safety is one of key areas being considered in the NUE fuel application in the Qinshan CANDU reactor. The impact of using NUE fuel on safety is minimized by the fact that the NUE fuel is designed and fabricated to be similar to natural uranium fuel in terms of reactor physics and thermalhydraulics. To assess the potential impact of NUE fuel on safety, a safety screening and evaluation was performed for the NUE fuel application based on the existing safety analyses reported in the Qinshan CANDU FSAR. The safety implication of using NUE fuel in two channels in the CANDU reactor is assessed from a safety margin point of view. The events are screened out for further consideration if it is judged that their safety analyses are not affected by using NUE fuel in two fuel channels.
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