Waste Management Assessment of Candidate Materials for HiPER Reaction Chamber

Sanz, J.; Juárez, R.; Ognissanto, F.; Perlado, J.M.

doi:10.13182/fst11-a12445

Cited by 3 publications

(7 citation statements)

References 13 publications

(25 reference statements)

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“…Considering the results of the previous design [1,2], together with the obtained results, we can conclude that outside the Bioshield, workers may stand during the operation of the facility. In effect, it was already a free-exclusion area in the previous design, and in the current design, there are bigger shields.…”

Section: Dose To Workersmentioning

confidence: 56%

“…As it will be necessary for the chamber to exert some structural functions, aluminum alloys are definitively abandoned as candidate materials for the reaction chamber in benefit of steel alloys. Commercial T91 steel has been selected from a previous study [2] for waste management considerations.…”

Section: Baseline Designmentioning

confidence: 99%

“…We perform a waste management assessment (WMA) of all the components inside the target bay to support the decision making on the choice of materials and also to estimate and show general trends about the management of the activated material. This study of the WMA is the continuity of [2], where we evaluated the behavior of different steels for the reaction chamber.…”

Section: Decommissioningmentioning

confidence: 99%

“…A preliminary integrated design, coupling optical systems together with shields against neutrons and gammas, was evaluated from the standpoint of radiological assessment [1]. A deep study was also accomplished on the materials selection for the reaction chamber [2]. Linking the conclusions of those studies [1,2] to some changes in the baseline design, a new and advanced design of HiPER 4a target bay is ready.…”

Section: Introductionmentioning

confidence: 99%

“…A deep study was also accomplished on the materials selection for the reaction chamber [2]. Linking the conclusions of those studies [1,2] to some changes in the baseline design, a new and advanced design of HiPER 4a target bay is ready. In this advanced design three systems are integrated: optical systems, remote maintenance systems and shielding requirements.…”

Section: Introductionmentioning

confidence: 99%

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Advances in neutronics and radiological protection of HiPER 4a

Juárez¹,

Sanz

Perlado³

2012

Fusion Engineering and Design

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a b s t r a c tThe HiPER project, phase 4a, is evolving. In this study we present the progress made in the field of neutronics and radiological protection for an integrated design of the facility. In the current model, we take into account the optical systems inside the target bay, as well as the remote handling requirements and related infrastructure, together with different shields. The last reference irradiation scenario, consisting of 20 MJ of neutron yields, 5 yields per burst, one burst every week and 30 years of expected lifetime is considered for this study. We have performed a characterization of the dose rates behavior in the facility, both during operation and between bursts. The dose rates are computed for workers, regarding to maintenance and handling, and also for optical systems, regarding to damage. Furthermore, we have performed a waste management assessment of all the components inside the target bay. Results indicate that remote maintenance is mandatory in some areas. The small beam penetrations in the shields are responsible for some high doses in some specific locations. With regards to optics, the residual doses are as high as prompt doses. It is found that the whole target bay may be fully managed as a waste in 30 years by recycling and/or clearance, with no need for burial.

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Section: Dose To Workersmentioning

confidence: 56%

Section: Baseline Designmentioning

confidence: 99%

Section: Decommissioningmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Advances in neutronics and radiological protection of HiPER 4a

Juárez¹,

Sanz

Perlado³

2012

Fusion Engineering and Design

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Thermo-fluid dynamics and corrosion analysis of a self cooled lead lithium blanket for the HiPER reactor

et al. 2015

Self Cite

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The HiPER reactor is the HiPER project phase devoted to power production. To reach a preliminary reactor design, tritium breeding schemes need to be adapted to the HiPER project technologies selection: direct drive ignition, 150 × MJ/shot 10 Hz of power released through fusion reactions, and the dry first wall scheme. In this paper we address the main challenge of the HiPER EUROFER-based self cooled lead lithium blanket, which is related to the corrosive behavior of Pb-15.7Li in contact with EUROFER. We evaluate the cooling and corrosion behavior of the so-called separated first wall blanket (SFWB) configuration by performing thermo-fluid dynamics simulations using a large eddy simulation approach. Despite the expected improvement over the integrated first wall blanket, we still find an unsatisfactory cooling performance, expressed as a low outlet Pb-15.7Li temperature plus too high corrosion rates derived from local Pb-15.7Li high temperature and velocity, which can mainly be attributed to the geometry of the channels. Nevertheless, the analysis allowed us to devise future modifications of the SFWB to overcome the limitations found with the present design.

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IFE plant technology overview and contribution to HiPER proposal

et al. 2011

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HiPER is the European Project for Laser Fusion that has been able to join 26 institutions and signed under formal government agreement by 6 countries inside the ESFRI Program of the European Union (EU). The project is already extended by EU for two years more (until 2013) after its first preparatory phase from 2008. A large work has been developed in different areas to arrive to a design of repetitive operation of Laser Fusion Reactor, and decisions are envisioned in the next phase of Technology Development or Risk Reduction for Engineering or Power Plant facilities (or both). Chamber design has been very much completed for Engineering phase and starting of preliminary options for Reactor Power Plant have been established and review here.

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Waste Management Assessment of Candidate Materials for HiPER Reaction Chamber

Abstract: One of the critical decisions in the HiPER

Cited by 3 publications

References 13 publications

Advances in neutronics and radiological protection of HiPER 4a

Advances in neutronics and radiological protection of HiPER 4a

Thermo-fluid dynamics and corrosion analysis of a self cooled lead lithium blanket for the HiPER reactor

IFE plant technology overview and contribution to HiPER proposal

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