Subjects: Energy Science >> Energy Science (General) Subjects: Nuclear Science and Technology >> Engineering Technology of Fission Reactor Subjects: Nuclear Science and Technology >> Particle Accelerator Subjects: Nuclear Science and Technology >> Reprocessing Technology of Spent Nuclear Fuel submitted time 2024-06-30
Abstract: Accelerator Driven sub-critical System (ADS) is considered to be the most important candidate for nuclear waste transmutation. We propose a Multi-Target Accelerator Driven System (MTADS) to resolve two longstanding challenges of ADS, namely heat removal and the associated target lifetime, and inhomogeneous power distribution that affects burn-up of the reactor. An 18 mA, 1 GeV proton beam is split into 12 beams by radio frequency cavities and injected to 12 compact targets inside the reactor. With beam power of 18 MW, the sub-critical reactor is driven to 1500 MW thermal power. The peaking factor of the reactor is reduced to 1.7 by optimization of targets number and position for Multi Target Accelerator Driven System. The maximum beam current density is also reduced to 18.5 μA/cm2, which prolongs the beam window lifetime to 12 months with T91 steel. Towards the next generation ADS, the concept of MTADS simplifies the sub-critical system and increases the transmutation efficiency.
Peer Review Status:Awaiting Review
Subjects: Physics >> Nuclear Physics Subjects: Nuclear Science and Technology >> Reprocessing Technology of Spent Nuclear Fuel submitted time 2023-06-20
Abstract: First principle is applied to the calculation of thermal neutron cross section of thermal neutron scattering materials in nuclear engineering field. In this paper, Al and Bi metals are used as examples to make thermal neutron cross section, respectively, based on the first principle, the frozen phonon method and density functional perturbation method are used. Using VASP and PHONONY, the phonon dispersion relation and phonon state density were calculated. Based on NJOY, Bi coherent scattering was added to LEAPR, and the thermal neutron scattering cross-section libraries of Al and Bi were generated. Results show that for Al, compared with the frozen phonon method, thermal neutron scattering cross section obtained by the density functional perturbation theory is in good agreement with ENDF8.0. For Bi, the imaginary frequency phenomenon of the frozen phonon method is eliminated by density functional perturbation method, and the results of thermal neutron scattering are in good agreement with the experimental results. In this paper, a more basic and predictable method for generating thermal neutron cross-section is proposed from the aspect of exploring the internal characteristic mechanism of the material, which lays a theoretical foundation for studying the thermal mechanism of the nuclear material of the new reactor.
Subjects: Nuclear Science and Technology >> Reprocessing Technology of Spent Nuclear Fuel submitted time 2022-05-28
Abstract:
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Peer Review Status:Awaiting Review