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A fusion–fission hybrid reactor with water-cooled pressure tube blanket for energy production
Affiliation:1. Department of Engineering, University of Palermo, Palermo, Italy;2. ENEA FSN-ING-PAN, ENEA CR Brasimone, Camugnano, Italy;3. Karlsruhe Institute of Technology (KIT), Institute for Neutron Physics and Reactor Technology (INR), Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen, Germany;1. Department of Physics, Faculty of Science, University of Zanjan, Zanjan, Iran;2. Physics Department, Faculty of Science, Imam Hossein Comprehensive University, Tehran, Iran;3. Department of Physics, Faculty of Science, Imam Khomeini International University, Qazvin, Iran;1. Associazione EURATOM-ENEA, Department of Industrial Engineering, University of Rome “Tor Vergata”, Via del Politecnico 1, 00133 Rome, Italy;2. Grupo de Tratamiento de Imágenes, E.T.S.I de Telecomunicación, Universidad Politécnica de Madrid, Spain;3. EURATOM/CCFE Association, Culham Science Centre, Abingdon, United Kingdom;4. Video Processing and Understanding Laboratory, Universidad Autónoma de Madrid, Spain;1. Dipartimento di Energia, Ingegneria dell’Informazione e Modelli Matematici, Università di Palermo, Viale delle Scienze, I-90128 Palermo, Italy;2. ENEA C.R. Brasimone, Camugnano, I-40032 Bologna, Italy
Abstract:A fusion–fission hybrid reactor is proposed to achieve the energy gain of 3000 MW thermal power with self-sustaining tritium. The hybrid reactor is designed based on the plasma conditions and configurations of ITER, as well as the well-developed pressurized light water cooling technologies. For the sake of safety, the pressure tube bundles are employed to protect the first wall from the high pressure of coolant. The spent nuclear fuel discharged from 33GWD/tU Light Water Reactors (LWRs) and natural uranium oxide are taken as driver fuel for energy multiplication. According to thermo-mechanics calculation results, the first wall of 20 mm is safe. The radiation damage analysis indicates that the first wall has a lifetime of more than five years. Neutronics calculations show that the proposed hybrid reactor has high energy multiplication factor, tritium breeding ratio and power density; the fuel cannot reach the level of plutonium required for a nuclear weapon. Thermal-hydraulic analysis indicates that the temperatures of the fuel zone are well below the limited values and a large safety margin is provided.
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