8 research outputs found

    Utilization of the BARC critical facility for ADS related experiments

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    Nuclear data sensitivity studies towards understanding of fuel temperature coefficient in AHWR

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    The Advanced Heavy Water Reactor (AHWR) is a 920 MWth, vertical pressure tube type thorium-based reactor cooled by natural convection by boiling light water and moderated by heavy water. In this paper, we present the isotopic and energy group wise contributions to the Fuel Temperature Coefficient (FTC) in AHWR using our first order perturbation analysis code. In AHWR, the contribution of 239Pu to FTC decreases with burn-up and the contribution of 233U in FTC becomes more negative with burn-up. Also 232Th gives a significant negative contribution, which makes the FTC become more negative with burn-up in AHWR

    The IAEA CRP on Studies of Advanced Reactor Technology Options for Effective Incineration of Radioactive Waste

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    In 2003, the IAEA has initiated the Coordinated Research Project (CRP) on ¿Studies of Advanced Reactor Technology Options for Effective Incineration of Radioactive Waste¿. The overall objective of the CRP, performed within the framework of IAEA¿s Nuclear Energy Department¿s Technical Working Group on Fast Reactors, is to increase the capability of Member States in developing and applying advanced technologies in the area of long-lived radioactive waste utilization and transmutation. Twenty institutions from 15 Member States and one international organization participated in this CRP. The CRP concentrated on the assessment of the dynamic behavior of various transmutation systems. The reactor systems investigated comprise critical reactors, sub-critical accelerator driven systems with heavy liquid metal and gas cooling, critical molten salt systems, and hybrid fusion/fission systems. Both fertile and fertile-free fuel options have been investigated. Apart from the benchmarking of steady state core configurations (including the investigation of transmutation potential, burn-up behavior and decay heat of minor actinide (MA) bearing fuels), the CRP participants determined the safety coefficients for the individual systems and, in a second stage, performed transient analyses which reflected the generic safety related behavior of the various reactors types.JRC.F.4-Safety of future nuclear reactor

    REPORT ON INTERMEDIATE RESULTS OF THE IAEA CRP ON STUDIES OF ADVANCED REACTOR TECHNOLOGY OPTIONS FOR EFFECTIVE INCINERATION OF RADIOACTIVE WASTES

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    In 2003 the IAEA has initiated a Coordinated Research Project (CRP) on ‘‘Studies of Advanced Reactor Technology Options for Effective Incineration of Radioactive Waste". Major intermediate results have been obtained and will be reported here. The overall objective of the CRP, performed within the framework of IAEA's Nuclear Energy's Department Technical Working Group on Fast Reactors, is to increase the capability of Member States in developing and applying advanced technologies in the area of long-lived radioactive waste utilization and transmutation. Sixteen institutions from 12 member states and one international organization participated in this CRP. The CRP concentrated on the assessment of the dynamic behaviour of various transmutation systems. The reactor systems investigated comprise critical reactors, subcritical accelerator driven systems with heavy liquid metal and gas cooling, critical molten salt systems and hybride fusion/fission systems. Both fertile and fertile-free fuel options have been investigated. For a deep assessment of the transient and safety behaviour, the analytical capabilities have to be qualified. A major effort of the CRP consisted in the benchmarking of steady state core configurations and performing transient/accident simulations. For a general assessment and comparison, the safety coefficients were determined for the individual systems. In a second step transient analyses were performed which reflected the generic behaviour of the various reactors types. In addition the transmutation potential, burn-up behaviour and decay heat of minor actinide bearing fuels were investigate

    REPORT ON INTERMEDIATE RESULTS OF THE IAEA CRP ON STUDIES OF ADVANCED REACTOR TECHNOLOGY OPTIONS FOR EFFECTIVE INCINERATION OF RADIOACTIVE WASTES

    No full text
    In 2003 the IAEA has initiated a Coordinated Research Project (CRP) on ‘‘Studies of Advanced Reactor Technology Options for Effective Incineration of Radioactive Waste”. Major intermediate results have been obtained and will be reported here. The overall objective of the CRP, performed within the framework of IAEA’s Nuclear Energy’s Department Technical Working Group on Fast Reactors, is to increase the capability of Member States in developing and applying advanced technologies in the area of long-lived radioactive waste utilization and transmutation. Sixteen institutions from 12 member states and one international organization participated in this CRP. The CRP concentrated on the assessment of the dynamic behaviour of various transmutation systems. The reactor systems investigated comprise critical reactors, subcritical accelerator driven systems with heavy liquid metal and gas cooling, critical molten salt systems and hybride fusion/fission systems. Both fertile and fertile-free fuel options have been investigated. For a deep assessment of the transient and safety behaviour, the analytical capabilities have to be qualified. A major effort of the CRP consisted in the benchmarking of steady state core configurations and performing transient/accident simulations. For a general assessment and comparison, the safety coefficients were determined for the individual systems. In a second step transient analyses were performed which reflected the generic behaviour of the various reactors types. In addition the transmutation potential, burn-up behaviour and decay heat of minor actinide bearing fuels were investigated
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