Validation of liquid lithium target stability for an intense neutron source

Kondo, Hiroo; Kanemura, Takuji; Furukawa, Tomohiro; Hirakawa, Yasushi; Wakai, Eiichi; Knaster, J.

doi:10.1088/1741-4326/aa5fbd

Cited by 20 publications

(6 citation statements)

References 15 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…The lithium target design is based on the results of IFMIF/EVEDA lithium target loop (ELTL) test. The ELTL has achieved high and stable Li flow up to 20 m s −1 and long operation [10]. In order to acquire a considerable number of RAFM post irradiation data by 2035, the A-FNS should integrate with the PIE facility.…”

Section: Parameters and Components Of A-fnsmentioning

confidence: 99%

Conceptual design progress of advanced fusion neutron source

et al. 2020

Self Cite

View full text Add to dashboard Cite

Based on the results of the IFMIF/EVEDA project in the broader approach (BA) activities, the conceptual design of the Advanced Fusion Neutron Source (A-FNS) to obtain irradiation data of DEMO blanket materials is under consideration in Japan. This paper describes the progress of the A-FNS conceptual design, which consists of a 40 MeV, 125 mA deuteron beam, a liquid lithium target system, and a test and post-irradiation test facilities. the main objectives of the A-FNS are the acquisition of RAFM irradiation data up to 2035 and the tritium recovery test on the blanket. In addition, it is expected to be used for various neutron researches. The technical design activities of the A-FNS are focused on improvement of the lithium target design, review of impurity criteria, remote handling, and irradiation application plan.

show abstract

Section: Parameters and Components Of A-fnsmentioning

confidence: 99%

Conceptual design progress of advanced fusion neutron source

et al. 2020

Self Cite

View full text Add to dashboard Cite

show abstract

“…The stability of the liquid lithium target, as requested from stringent requirements, has been widely demonstrated both by numerical simulations and exper imental tests on the facility EVEDA lithium test loop (ELTL) in Oarai, Japan, [6,7]. -Other components of the target system are the target assembly (TA) support structure, the lithium inlet and outlet pipes and their shielding plugs, the beam ducts and their shielding plugs, and the quench tank (QT).…”

Section: Lithium Systems (Ls)mentioning

confidence: 99%

The European approach to the fusion-like neutron source: the IFMIF-DONES project

Ibarra

Arbeiter²,

Bernardi

et al. 2019

Nucl. Fusion

View full text Add to dashboard Cite

The need of a neutron source for the qualification of materials to be used in future fusion power reactors have been recognized in the European (EU) fusion programme since many years. The construction and exploitation of this facility is presently considered to be in the critical path of DEMO. This issue prompted the EU to launch activities for the design and engineering of the IFMIF-DONES (International Fusion Materials Irradiation Facility-DEMO Oriented Neutron Source) facility based on and taking profit of the results obtained in the IFMIF/EVEDA ('Engineering Validation and Engineering Design Activities') project, presently conducted in the framework of the EU-Japan Bilateral Agreement on the Broader Approach to Fusion. These activities and R&D work for the IFMIF-DONES Plant are presently taking place in the framework of a work package of the 'EUROfusion' Consortium, in direct collaboration with 'Fusion for Energy' Organization. The main objective of these activities is to consolidate the design and the underlying technology basis in order to be ready for IFMIF-DONES construction as early as possible. The paper presents the main engineering results for a generic site obtained during the first years of design work, as indicated in the recently released IFMIF-DONES Preliminary Engineering Design Report, making emphasis on the design evolution from previous phases and on the critical issues to be further developed in the near future. The proposed European site to host the facility (Granada Spain) is briefly introduced as well.

show abstract

“…• The demanding operational conditions of the 523 K Li screen flowing at 15 m s −1 with a 25 mm ± 1 mm thick screen in the beam footprint area (Bragg peak of 40 MeV deuteron in Li is 19 mm) were demonstrated as technically feasible in the successful long-term operation of the EVEDA lithium test loop in Oarai [93,94]. • The full scale prototype of the high flux test module (HFTM) housing the small specimens developed under the EVEDA Phase [95] demonstrated the feasibility of the thermalization of a full stack of ~80 capsules within ±3% at the specified temperature within 523 K and 823 K (in the HFTM of IFMIF, 12 capsules independently cooled will be housing ~80 small specimens each [96]).…”

Section: Liquid Targetsmentioning

confidence: 99%

An assessment of the available alternatives for fusion relevant neutron sources

Knaster¹

2018

Nucl. Fusion

Self Cite

View full text Add to dashboard Cite

The discovery of void swelling in neutron-irradiated stainless steels by Cawthorne and Fulton in 1966 showed that radiation effects would seriously affect the lifetime of fission reactors. A few years later, in the early 1970s, serious damage levels were observed in core components of the first commercial fission reactors that had been in operation for one decade. Driven by the harder neutron spectrum, the fusion community was impelled to explore the technical possibilities to make available a fusion relevant neutron source to anticipate the difficulties faced by the fission reactors community and ensure the long-term operation of a fusion reactor. In 1976, the conclusions of the first review published announced the assets and drawbacks of the different possibilities, which today despite the four decades passed and the sound technological advancements, continue being basically the same. A suitable neutron spectrum can be theoretically obtained both from plasma-based or accelerators based facilities with either gas, liquid or solids targets. Needed facilities performances, available irradiation volumes that the concept allow and cost are at stake. In the past, the cost of the most promising facility based on stripping the neutron from a deuteron on a lithium target was misleadingly peered with that of a fusion reactor. A tokamak with sufficient volume to irradiate equipment under fusion relevant conditions will be likely available in the future once commercial fusion reactors have become a reality; unfortunately, this concept does not match the needs timely, and is unrealistic w.r.t. its costs nowadays with worldwide efforts prioritizing ITER. In this article, we will focus on the technical aspects and assess the present maturity of different existing possibilities based on nowadays technologies to count with neutrons at a suitable flux and spectrum to characterize and qualify fusion materials to be timely ready with our world fusion roadmaps.

show abstract

Validation of liquid lithium target stability for an intense neutron source

Cited by 20 publications

References 15 publications

Conceptual design progress of advanced fusion neutron source

Conceptual design progress of advanced fusion neutron source

The European approach to the fusion-like neutron source: the IFMIF-DONES project

An assessment of the available alternatives for fusion relevant neutron sources

Contact Info

Product

Resources

About