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Perspectives
Published in Ivan G. Draganić, Zorica D. Draganić, Jean-Pierre Adloff, Radiation and Radioactivity on Earth and Beyond, 2020
Ivan G. Draganić, Zorica D. Draganić, Jean-Pierre Adloff
The tritium consumed in the process is regenerated in a breeding blanket made of lithium, according to: Neutron + 6Li →3H + 4HeNeutron + 7Li →3H + 4He + neutron
Safety assessment
Published in Stein Haugen, Anne Barros, Coen van Gulijk, Trond Kongsvik, Jan Erik Vinnem, Safety and Reliability – Safe Societies in a Changing World, 2018
A. Carpignano, S. Dulla, A.C. Uggenti
The PSA model begins with a systematic search of initiating events. Since the preliminary design stage of some of the new generation plants, a functional approach has been selected, suitable to define possible accident initiators when a sufficient design detail is not yet available to allow more specific evaluations at the component level. This methodology has already been applied on fusion devices, in particular to analyse the Primary Heat Transfer System (PHTS) of EU DEMO, with a WCLL (Water Cooled Lithium Lead) and a DCLL (Dual Coolant Lithium Lead) breeding blanket (Pinna, 2017), (Carpignano, 2016).
Energy Tomorrow
Published in Heinz Knoepfel, Energy 2000, 2017
The chain reaction takes place in the active core of the reactor, mainly with plutonium 239. In the outer breeding blanket a nonfissile nucleus (uranium 238) is transmuted into a fissile one (plutonium 239). The plutonium thus produced is recovered chemically in reprocessing plants and supplied as an active fuel for subsequent recharging of the same or other reactors.
Experimental Study on Mechanical Characteristics of Li2TiO3 Pebble Beds Under Cyclic Loading
Published in Fusion Science and Technology, 2023
Chongyang He, Cong Wang, Yong Liu, Lei Chen, Kun Zhang, Fujun Gou, Songlin Liu
The tritium breeding blanket is one of the key components of the fusion reactor, and its main functions are to realize tritium self-sufficiency, convert fusion energy into usable energy, and shield fusion neutrons to ensure the safe and stable operation of fusion reactor components.1,2 For the solid blanket, Li2TiO3, Li4SiO4, Li2O, and other lithium ceramic particles are generally used as the tritium breeder, and the neutron multiplier is beryllium (Be) or beryllium alloy. Specifically, the Li2TiO3 and Be12Ti mixed pebble bed with excellent tritium production performance is applied in the design of the water-cooled ceramic breeder (WCCB) blanket for the China Fusion Engineering Test Reactor (CFETR).
Modeling of Transport Processes in Liquid-Metal Fusion Blankets: Past, Present, and Future
Published in Fusion Science and Technology, 2023
In most of the current developments in LM breeding blankets in the United States and worldwide, the eutectic alloy lead lithium (PbLi) is used as the breeder/coolant and neutron multiplier, water or helium (He) gas is used as the coolant, and reduced activation ferritic martensitic (RAFM) steel is used as the structural material. In recent fusion nuclear science facility (FNSF) studies in the United States,4 a dual-coolant lead-lithium (DCLL) blanket5 has been considered as the most promising LM breeding blanket concept. Due to its many advantages compared to other blanket concepts, it is expected that the DCLL blanket will also be selected as the main breeding blanket candidate for the U.S. fusion pilot plant, the near-term future machine that will aim to produce net electricity from fusion over longer periods, test integration with the U.S. electric grid, and provide technical and economic information for a future first-of-a-kind commercial power plant.6
The Compactness and Inboard Radial Build of Fusion Nuclear Devices
Published in Fusion Science and Technology, 2021
C. E. Kessel, T. Bohm, M. S. Tillack, P. Titus, Y. Zhai
The primary structural material for the breeding blanket worldwide is RAFM steel.34 It has significant resistance to swelling, has low activation allowing qualification for shallow land burial after sufficient cooldown, and retains reasonable mechanical properties up to ~500°C. In general, this steel is used from the first wall to the back of the blanket, and mostly likely also for the structural ring. Table IV shows the peak values for neutron damage [displacements per atom (dpa)], helium production, and hydrogen production as one moves from the first wall to the LT shield.32,35 These values are correlated with the inboard peak neutron wall loading, which was 1.31 MW/m2 in the FNSF design. The fall-off of these quantities is substantial as one moves from the first wall into the subsequent components, however, the first wall, breeding blanket, and structural ring (as well as the divertor, RF launchers, diagnostic port plugs, and test modules) are replaceable, while the VV and LT shield are permanent components. When accumulating nuclear impacts, this demarcation must be recognized.