Feasibility of D-D start-up under realistic technological assumptions for EU-DEMO

Siccinio, M.; Chiovaro, P.; Cismondi, F.; Coleman, Matti; Day, Christian; Fable, E.; Federici, G.; Härtl, T.; Schwenzer, J.; Spagnuolo, Gandolfo Alessandro

doi:10.1016/j.fusengdes.2021.112554

Cited by 3 publications

(3 citation statements)

References 29 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…On the other hand, an operation scenario in which the amount of T required for start-up is gradually increased using T generated by DD operation is under study. In order to achieve steady operation by this method, DD operation is required for a long period of operation time and a large amount of power [16]. Therefore, the target value of overall TBR for the JA DEMO was assumed to be 1.05, which takes into account the provision of a start-up inventory of T for another fusion power plant.…”

Section: The Target Of the Tbr On The Calculationmentioning

confidence: 99%

Development of water-cooled cylindrical blanket in JA DEMO

Youji,

Hiroyasu,

Yoshiteru

2024

Nucl. Fusion

View full text Add to dashboard Cite

The concept of the tritium breeding blanket for Japan’s DEMOnstration fusion reactor (JA DEMO) has been developed with pressure tightness against in-box Loss-of-coolant accidents based on a water-cooled solid breeder concept. The cooling conditions are designed on the PWR (pressurized-water reactor) water conditions which are the coolant temperature of 290 ºC - 325 ºC and the operating pressure of 15.5 MPa, respectively. The point of the blanket design is to reduce the amount of structural material in casing as well as to ensure its pressure tightness. This is because a decrease in the amount of structural material improves TBR (Tritium Breeding Ratio). A cylindrical structure, a thin wall casing structure which ensures pressure tightness and could increase TBR, is feasible. However, a relatively larger useless space is expected between modules when the cylindrical blanket modules are arranged in a vacuum vessel, which could decrease TBR. Therefore, the cylindrical blanket modules are to be in a close-packed arrangement to reduce useless space. The Be12Ti block (which shows a minor swelling compared to Be) is selected to achieve the target TBR as the net Be density is equivalent to the case of the Be pebble. The use of Be12Ti blocks can reduce or remove the cooling piping inside the module as the Be12Ti block has a higher thermal conductivity than pebbles. As a result of the neutronics, Finite element method, and Computational Fluid Dynamics analyses, it was found that the target TBR value can be achieved in cylindrical structure blanket that ensure pressure tightness.

show abstract

Section: The Target Of the Tbr On The Calculationmentioning

confidence: 99%

Development of water-cooled cylindrical blanket in JA DEMO

Youji,

Hiroyasu,

Yoshiteru

2024

Nucl. Fusion

View full text Add to dashboard Cite

show abstract

“…[ 100 ] The world's only commercial sources are Canada Deuterium Uranium (CANDU) nuclear reactors whose operation in the next decades (both in terms of extending the life of existing reactors and constructing new ones) is now a matter of debate. [ 99 ] Owing to the large uncertainty and complex issues surrounding the variety of potential T 2 supply sources, there is a possibility that external T 2 will be unavailable for the start‐up of the DEMO fusion reactor around 2050. [ 96 ] In a worst‐case scenario, “it would appear that there is insufficient tritium to satisfy the fusion demand after ITER.” [ 100 ] As the tritium inventory for the fuel‐cycle start‐up is a vital parameter, its sufficiency is one of the key issues remaining to be solved in upcoming fusion reactors.…”

Section: Importance Of Fusion Energy Tritium Inventories and Deuteriu...mentioning

confidence: 99%

“…Tritium, with a half-life of 12.3 years, is the prime fuel used in fusion reactors, and is hardly found in nature. [99,100] Fusion reactors generally need a large startup T 2 supply. If this quantity is very large, the availability of T 2 from other global sources may not be sufficient to meet the demand.…”

Section: Tritium Inventoriesmentioning

confidence: 99%

Recent Progress in Functional Nanomaterials towards the Storage, Separation, and Removal of Tritium

et al. 2023

View full text Add to dashboard Cite

Tritium is a sustainable next‐generation prime fuel for generating nuclear energy through fusion reactions to fulfill the increasing global energy demand. Owing to the scarcity–high demand tradeoff, tritium must be bred inside a fusion reactor to ensure sustainability and must therefore be separated from its isotopes (protium and deuterium) in pure form, stored safely, and supplied on demand. Existing multistage isotope separation technologies exhibit low separation efficiency and require intensive energy inputs and large capital investments. Furthermore, tritium‐contaminated heavy water constitutes a major fraction of nuclear waste, and accidents like the one at Fukushima Daiichi leave behind thousands of tons of diluted tritiated water, whose removal is beneficial from an environmental point of view. In this review, we discuss the recent progress and main research trends in hydrogen isotope storage and separation by focusing on the use of metal hydride (e.g., intermetallic, and high‐entropy alloys), porous (e.g., zeolites and metal organic frameworks (MOFs)), and 2‐D layered (e.g., graphene, hexagonal boron nitride (h‐BN), and MXenes) materials to separate and store tritium based on their diverse functionalities. Finally, the challenges and future directions for implementing tritium storage and separation are summarized in the reviewed materials.This article is protected by copyright. All rights reserved

show abstract