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[en] The report presents the design features of KLFR; Safety Analysis Code; steady-state calculation results and analysis results of unscrammed events. The calculations of the steady-state and unscrammed events have been performed for the conceptual design of KLFR using SSC-K code. UTOP event results in no fuel damage and no centre-line melting. The inherent safety features are demonstrated through the analysis of ULOHS event. Although the analysis of ULOF has much uncertainties in the pump design, the analysis results show the inherent safety characteristics. 6% flow of rated flow of natural circulation is formed in the case of ULOF. In the metallic fuel rod, the cladding temperature is somewhat high due to the low heat transfer coefficient of lead. ULOHS event should be considered in design of RVACS for long-term cooling

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[en] The project 'Basic Research for Physics and Technologies Related to Accelerator Driven Clean Nuclear Energy System' is presented. For the purpose of transmutation, MAs should be burned up as much as possible during a burnup cycle so that MAs will not be dropped into tailings.In order to lengthen cycle and reduce the requisition to the power of accelerator, k_eff should remain stable in the course of a burn-up cycle. The design of ADS, model set-up and the result from the calculations are presented

[en] Molten Salt reactor have promising properties to realize transmutation of long-lived nuclear waste. Widespread general purpose Monte Carlo code is capable to simulate the delayed neutrons in all details. Modification is needed to account for the transport of the delayed neutron precursors. MCNP4C with appropriate modifications is applicable to model the reactivity loss due to circulating fuel.With the variance reduction technique it is possible to investigate minor 3D effect, or fullscale MSR concepts. MOSART concept results need further investigation

[en] The Technical Meeting held at the Institute of Plasma Physics, Chinese Academy of Sciences (ASIPP) in Hefei was the second Research Coordination Meeting (RCM) of the CRP on 'Studies of Innovative Reactor Technology Options for Effective Incineration of Radioactive Waste'. All but one Member States participating in the CRP were attending: in all, 26 participants from 13 Member States and three international organizations. The overall objective of the CRP is to increase the capability of Member States in developing and applying advanced nuclear technologies in the area of long-lived radioactive waste utilization and transmutation. The final goal of the CRP is to deepen the understanding of the dynamics of transmutation systems, e.g., the accelerator driven system, especially of systems with deteriorated safety parameters, to qualify the available methods, specify the range of validity of these methods, and formulate requirements for future theoretical developments. Should transient experiments be available, the CRP will pursue experimental benchmarking work. Based on the results, the CRP will conclude on the potential need of transient experiments and make appropriate proposals for experimental programs. The scope of the second RCM was to review the progress achieved with regard on the technical work of the CRP. In particular, the main objectives of the RCM were to (a) analyse and inter-compare the individual results; (b) identify of eventual changes/improvements to the tasks and/or work plans; (c) plan the next stage(s); and (d) start preparation of the final CRP report. The participants were given a brief overview of the Institute's mission and accomplishments. ASIPP (Academia Sinica, Institute of Plasma Physics) was founded in 1978 as the leading centre for high temperature plasma physics, magnetically confined fusion technology, as well as R and D in related technological areas. ASIPP employs nearly 500 staff, of which more than 70% are scientists or engineers. The institute has two experimental facilities for controlled fusion R and D: the HT-6M, a small-scale conventional Tokamak, and the HT-7, the first super-conducting toroidal magnetic field coils, circular cross-section Tokamak in China. Presently, ASIPP is constructing a new Tokamak, the D-shape cross section HT-7U (also called EAST) that will have super-conducting magnetic field coils for both plasma generation and confining (during lunch break, the participants were given the opportunity to visit these facilities). All RCM objectives were attained. A summary of the main results and conclusions is given below. The CRP's benchmarking exercises focus on eight innovative transmutation 'domains' (which correspond to different critical and sub-critical concepts or groups of concepts): I. Critical fast reactor, solid fuel, with fertile II. Critical fast reactor, solid fuel, fertile-free III. ADS, solid fuel, with fertile IV. ADS, solid fuel, fertile-free V. Critical reactor and ADS, molten salt fuel, with fertile VI. Critical reactor and ADS, molten salt fuel, fertile-free VII. Critical fast reactor and ADS, gas cooled VIII. Fusion/fission hybrid system

[en] The major characteristics of the Molten Salt Reactor are presented and examples of the activities in this area are given. MOSART kinetic data is presented. Transients recommended to be analysed for MOSART Molten Salt Reactor Concept are established and some limitations to be considered are outlined. Preliminary observations that can be made as regards the MOSART Molten Salt concepts are: 1. the critical MOSART design is immune to most unprotected transients except the UTOP transient (fuel agglomeration issue in piping system). 2. If fuel agglomeration issue should be an issue, we need to a). assess how large (in terms of reactivity) potential fuel particles could be, b). if fuel particles are below 300 pcm then design should be a 'critical' design. c). if fuel particles can be in excess of 500 pcm, then should consider core design to be 'sub-critical'. 3. If reactor design is 'sub-critical', then must be aware that the transient characteristics of sub-critical systems is less favourable to most unprotected transients in comparison to protected transients

[en] the LBE-cooled XADS concept (as designed by ANSALDO) was an already available, well documented, nearly optimally iterated core and plant design.The design of the core and plant layout of He-cooled XADS concept was initiated at the start of PDS-XADS project. The current design is not fully optimized/iterated.The spectrum of transients analysed for each XADS Design (LBE and He cooled), computer codes and Criteria of Safety for PDS-XADS Transient Study are presented in the report, as well as some important limitations.The general observations that can be made as regards the He-cooled XADS concepts are: 1. with careful design and optimization of all the various core and plant design features in combination with an optimized plant I and C, the response of the He-cooled XADS concept can be demonstrated to stay within the safety limits for the most likely, protected transient initiators, 2. improvements in plant design are possible for further optimization of the response of the plant to DEC protected transients