Evolution of beryllium pebbles (HIDOBE) in long term, high flux irradiation in the high flux reactor

Til, S. van; Hegeman, J.B.J.; Cobussen, H.L.; Stijkel, M.P.

doi:10.1016/j.fusengdes.2011.01.079

Cited by 26 publications

(14 citation statements)

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“…9b). Considerable swelling (∼12%) observed at this temperature [3] and previous X-Ray-absorption tomography studies [19,20] suggest a possibility of the open porosity network formation which can explain the decrease of total tritium and helium release with increasing irradiation temperature (see Figs. 4 and 5a).…”

Section: Microstructuresupporting

confidence: 67%

“…The irradiation parameters of the investigated beryllium pebbles are summarized in Table 2 [2,3]. The temperatures during irradiation were measured by thermocouples located close to the containers with the beryllium pebbles.…”

Section: Methodsmentioning

confidence: 99%

“…The long-term neutron irradiation of beryllium pebbles has been performed in the HIDOBE-01 experiment in the High Flux Reactor (HFR), Petten, the Netherlands on 2005-2007 [2,3]. The investigated beryllium pebbles were irradiated at 686-1006 K up to 3000 appm helium and 300 appm tritium productions, accordingly.…”

Section: Introductionmentioning

confidence: 99%

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Tritium release from highly neutron irradiated constrained and unconstrained beryllium pebbles

Chakin

Rolli

Vladimirov

et al. 2015

Fusion Engineering and Design

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Section: Microstructuresupporting

confidence: 67%

Section: Methodsmentioning

confidence: 99%

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Tritium release from highly neutron irradiated constrained and unconstrained beryllium pebbles

Chakin

Rolli

Vladimirov

et al. 2015

Fusion Engineering and Design

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“…Upon the successful development of plasma-assisted sintered beryllide rod [43] for use in the rotating electrode method for titanium beryllide pebble production, titanium beryllide is a promising potential replacement to pure Be as a neutron multiplier for ceramic breeder blankets for DEMO. It has already been shown in recent irradiation data from HIDOBE-1 and HIDOBE-2 [44] that helium production that at high temperature such as 750 • C titanium beryllide has significantly less volumetric swelling of 12% as compared to about 22% of the pure Be at 30% of the DEMO End-of-Life [41].…”

Section: Solid Breeder Blanket Conceptsmentioning

confidence: 99%

“…The out-of-pile temperature programmed desorption (TPD) tritium release measurements for the samples from HIDOBE-1 and HIDOBE-2 [44] have shown that tritium retention in Be is about 100% at irradiated temperatures below 525 • C [41,92,93], while titanium beryllides show only 30-50% of tritium retention at 425 • C and virtually no retention at higher temperatures [41]. This result of low tritium retention in beryllide seems very encouraging as the data has shown swelling can be a concern at high temperatures.…”

Section: Tritium Release Inventory and Control (Solid Breeder)mentioning

confidence: 99%

Blanket/first wall challenges and required R&D on the pathway to DEMO

Abdou

Morley

Smolentsev

et al. 2015

Fusion Engineering and Design

276

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a b s t r a c tThe breeding blanket with integrated first wall (FW) is the key nuclear component for power extraction, tritium fuel sustainability, and radiation shielding in fusion reactors. The ITER device will address plasma burn physics and plasma support technology, but it does not have a breeding blanket. Current activities to develop "roadmaps" for realizing fusion power recognize the blanket/FW as one of the principal remaining challenges. Therefore, a central element of the current planning activities is focused on the question: what are the research and major facilities required to develop the blanket/FW to a level which enables the design, construction and successful operation of a fusion DEMO? The principal challenges in the development of the blanket/FW are: (1) the Fusion Nuclear Environment -a multiple-field environment (neutrons, heat/particle fluxes, magnetic field, etc.) with high magnitudes and steep gradients and transients; (2) Nuclear Heating in a large volume with sharp gradients -the nuclear heating drives most blanket phenomena, but accurate simulation of this nuclear heating can be done only in a DT-plasma based facility; and (3) Complex Configuration with blanket/first wall/divertor inside the vacuum vessel -the consequence is low fault tolerance and long repair/replacement time.These blanket/FW development challenges result in critical consequences: (a) non-fusion facilities (laboratory experiments) need to be substantial to simulate multiple fields/multiple effects and must be accompanied by extensive modeling; (b) results from non-fusion facilities will be limited and will not fully resolve key technical issues. A DT-plasma based fusion nuclear science facility (FNSF) is required to perform "multiple effects" and "integrated" experiments in the fusion nuclear environment; and (c) the Reliability/Availability/Maintainability/Inspectability (RAMI) of fusion nuclear components is a major challenge and is one of the primary reasons why the blanket/FW will pace fusion development toward a DEMO.This paper summarizes the top technical issues and elucidates the primary challenges in developing the blanket/first wall and identifies the key R&D needs in non-fusion and fusion facilities on the path to DEMO.Published by Elsevier B.V. This is an open access article under the CC BY-NC-ND license (http:// creativecommons.org/licenses/by-nc-nd/4.0/).

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