Progress in developing the K-DEMO device configuration

Brown, Thomas G.; Kim, K.; Kessel, C.; Neilson, G.H.; Titus, P.; Zolfaghari, A.; Baik, Soonhyun; Im, Kyongok; Kim, H.-C; Lee, G.-S; Lee, Y.-S; Oh, S.; Yeom, Junho

doi:10.1109/sofe.2013.6635304

Cited by 6 publications

(4 citation statements)

References 4 publications

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“…To be in alignment with blankets sectors, the upper or lower divertor is also subdivided into 32 modules, respectively. To allow radial space for the vertical extraction of larger blanket modules, the outboard 2200-3000 Net electric power (MWe) 400-700 radius of the TF coil is enlarged, with a space of ∼2.5 m between the blanket modules and the outboard wall of the VV [2].…”

Section: Introductionmentioning

confidence: 99%

Design concept of K-DEMO for near-term implementation

Kim

et al. 2015

Nucl. Fusion

110

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A Korean fusion energy development promotion law (FEDPL) was enacted in 2007. As a following step, a conceptual design study for a steady-state Korean fusion demonstration reactor (K-DEMO) was initiated in 2012. After the thorough 0D system analysis, the parameters of the main machine characterized by the major and minor radii of 6.8 and 2.1 m, respectively, were chosen for further study. The analyses of heating and current drives were performed for the development of the plasma operation scenarios. Preliminary results on lower hybrid and neutral beam current drive are included herein. A high performance Nb3Sn-based superconducting conductor is adopted, providing a peak magnetic field approaching 16 T with the magnetic field at the plasma centre above 7 T. Pressurized water is the prominent choice for the main coolant of K-DEMO when the balance of plant development details is considered. The blanket system adopts a ceramic pebble type breeder. Considering plasma performance, a double-null divertor is the reference configuration choice of K-DEMO. For a high availability operation, K-DEMO incorporates a design with vertical maintenance. A design concept for K-DEMO is presented together with the preliminary design parameters.

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Section: Introductionmentioning

confidence: 99%

Design concept of K-DEMO for near-term implementation

Kim

et al. 2015

Nucl. Fusion

110

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“…To consider blanket heat generation in the vacuum vessel, primary heat transfer system of Korean demonstration reactor is modeled. Main information of blanket heat transfer system referred to Kim et aland other systems referred from . Preliminary design of fusion demonstration reactor has 16 equivalent sectors, which consist of outboard blanket and inboard blanket.…”

Section: Melcor Modeling For Korean Demomentioning

confidence: 99%

Analysis of hydrogen and dust explosion after vacuum vessel rupture: Preliminary safety analysis of Korean fusion demonstration reactor using MELCOR

2017

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SummaryHydrogen explosion is one of the most dangerous accident phenomena in both nuclear fusion and fission reactor. In the typical fusion reactor, tritium and deuterium are fuel elements for fusion reaction, and they exist in condensed state around the cryo-pump in the normal operation condition. In the accident situation, increasing heat transfer system temperature can mobilize lots of tritium in the vacuum vessel. And then, coolant can react with high-temperature structures generating hydrogen gas inside vacuum vessel. In addition, air ingress into plasma terminates fusion reaction producing activated dust on the first wall plasma facing surfaces. Through these series of process, mobilized tritium and dust aerosol can explode in the vacuum vessel and damage the containment building integrity, making a sort of source term leakage to environment through various system volumes. In this paper, preliminary safety analysis for hydrogen and dust explosion accident for assumed design of Korean fusion demonstration reactor is conducted. An MELCOR system analysis code is used to simulate this accident and parametric analysis to investigate effect on the accident scale and safety systems like detritiation system such as heating, ventilation, and air conditioning isolation system and pressure suppression system. As a result, aerosol distribution of each control volume and its release route are estimated, and final aerosol release to the environment is compared with release guideline for ITER. The amount of mobilized aerosol in demonstration reactor is evaluated conservatively using ITER normal operation condition.

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“…3. We have Designed XD/SXD for Demo reactors under a variety of assumptions (e.g., vertical maintenance for K-Demo [38,39], or the more ITER-like CREST design [40]). …”

Section: Simulations Of Experiments With Advanced Divertorsmentioning

confidence: 99%

Taming the Heat Flux Problem: Advanced Divertors Towards Fusion Power

et al. 2015

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The next generation fusion machines are likely to face enormous heat exhaust problems. In addition to summarizing major issues and physical processes connected with these problems, we discuss how advanced divertors, obtained by modifying the local geometry, may yield workable solutions. We also point out that: (1) the initial interpretation of recent experiments show that the advantages, predicted, for instance, for the X-divertor (in particular, being able to run a detached operation at high pedestal pressure) correlate very well with observations, and (2) the X-D geometry could be implemented on ITER (and DEMOS) respecting all the relevant constraints. A roadmap for future research efforts is proposed.

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Progress in developing the K-DEMO device configuration

Cited by 6 publications

References 4 publications

Design concept of K-DEMO for near-term implementation

Design concept of K-DEMO for near-term implementation

Analysis of hydrogen and dust explosion after vacuum vessel rupture: Preliminary safety analysis of Korean fusion demonstration reactor using MELCOR

Taming the Heat Flux Problem: Advanced Divertors Towards Fusion Power

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