Fusing together an outline design for sustained fuelling and tritium self-sufficiency

M Lord, I Bennett, C Harrington… - Philosophical …, 2024 - royalsocietypublishing.org
Ensuring tritium fuel self-sufficiency while maintaining continuous and high-specification fuel
flow to the tokamak via a low tritium inventory and controllable fuel cycle is a significant …

IFMIF: overview of the validation activities

J Knaster, F Arbeiter, P Cara, P Favuzza… - Nuclear …, 2013 - iopscience.iop.org
Abstract The Engineering Validation and Engineering Design Activities (EVEDA) for the
International Fusion Materials Irradiation Facility (IFMIF), an international collaboration …

The IFMIF-DONES project: design status and main achievements within the EUROfusion FP8 work programme

D Bernardi, A Ibarra, F Arbeiter, F Arranz… - Journal of Fusion …, 2022 - Springer
Abstract International Fusion Materials Irradiation Facility-DEMO-Oriented NEutron Source
(IFMIF-DONES) is a high-intensity neutron irradiation facility for qualification of fusion reactor …

Overview of the IFMIF/EVEDA projecta

J Knaster, P Garin, H Matsumoto, Y Okumura… - Nuclear …, 2017 - iopscience.iop.org
Overview of the IFMIF/EVEDA project - IOPscience Skip to content IOP Science home
Accessibility Help Search Journals Journals list Browse more than 100 science journal titles …

The accomplishment of the engineering design activities of IFMIF/EVEDA: the European–Japanese project towards a Li (d, xn) fusion relevant neutron source

J Knaster, A Ibarra, J Abal, A Abou-Sena… - Nuclear …, 2015 - iopscience.iop.org
Abstract The International Fusion Materials Irradiation Facility (IFMIF), presently in its
Engineering Validation and Engineering Design Activities (EVEDA) phase under the frame …

[HTML][HTML] IFMIF, the European–Japanese efforts under the Broader Approach agreement towards a Li (d, xn) neutron source: Current status and future options

J Knaster, F Arbeiter, P Cara, S Chel, A Facco… - Nuclear Materials and …, 2016 - Elsevier
The necessity of a neutron source for fusion materials research was identified already in the
70s. Though neutrons induced degradation present similarities on a mechanistic approach …

Recent progress in the NSTX/NSTX-U lithium programme and prospects for reactor-relevant liquid-lithium based divertor development

M Ono, MA Jaworski, R Kaita, HW Kugel, JW Ahn… - Nuclear …, 2013 - iopscience.iop.org
Developing a reactor-compatible divertor has been identified as a particularly challenging
technology problem for magnetic confinement fusion. Application of lithium (Li) in NSTX …

Conceptual design of advanced fusion neutron source (A-FNS) and irradiation test modules

S Sato, A Kasugai, K Ochiai, K Masuda… - Nuclear …, 2021 - iopscience.iop.org
We have established a conceptual design of Advanced Fusion Neutron Source (A-FNS). In
order to obtain irradiation data required in qualifying materials of fusion DEMO DT reactor …

Validation of liquid lithium target stability for an intense neutron source

H Kondo, T Kanemura, T Furukawa, Y Hirakawa… - Nuclear …, 2017 - iopscience.iop.org
This paper reports on validation results for the stability of a liquid lithium (Li) target intended
for use as an intense fusion neutron source such as for the International Fusion Materials …

IFMIF, a fusion relevant neutron source for material irradiation current status

J Knaster, S Chel, U Fischer, F Groeschel… - Journal of Nuclear …, 2014 - Elsevier
Abstract The d-Li based International Fusion Materials Irradiation Facility (IFMIF) will provide
a high neutron intensity neutron source with a suitable neutron spectrum to fulfil the …