Utilisation and Reliability of High Power Proton Accelerators
Workshop Proceedings, Daejeon, Republic of Korea, 16-19 May 2004
Accelerator-driven systems (ADS) are being considered for their potential use in the transmutation of radioactive waste. The performance of such hybrid nuclear systems depends to a large extent on the specification and reliability of high power accelerators, as well as the integration of the accelerator with spallation targets and sub-critical systems. At present, much R&D work is still required in order to demonstrate the desired capability of the system as a whole.
Accelerator scientists and reactor physicists from around the world gathered at an NEA workshop to discuss issues of common interest and to present the most recent achievements in their research. Discussions focused on accelerator reliability; target, window and coolant technology; sub-critical system design and ADS simulations; safety and control of ADS; and ADS experiments and test facilities. These proceedings contain the technical papers presented at the workshop as well as summaries of the working group discussions held. They will be of particular interest to scientists working on ADS development as well as on radioactive waste management issues in general.
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Design Study around Beam Window of ADS
Nuclear Energy Agency
The Japan Atomic Energy Research Institute (JAERI) is conducting the research and development (R&D) on the accelerator-driven subcritical system (ADS) for the effective transmutation of minor actinides (MAs). The ADS proposed by JAERI is an 800 MWth, Pb-Bi cooled, tank-type subcritical reactor loaded with nitride fuel (MA+Pu). Pb-Bi is also used as the spallation target. In this study, the feasibility of the ADS was discussed by focusing on the design around the beam window. The partition wall was placed between the target region and the ductless-type fuel assemblies to keep the good cooling performance for the hot-spot fuel pin. The flow control nozzle was installed to cool the beam window effectively. The thermal-hydraulic analysis showed that the maximum temperature at the outer surface of the beam window could be repressed below 500 C even in the case of maximum beam power (30 MW). The stress caused by the external pressure and the temperature distribution of the beam window was below the allowable limit.
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