ARIES-RS safety design and analysis

Steiner, D.; El-Guebaly, L.; Herring, Stephen; Khater, H. Y.; Mogahed, E.A.; Thayer, R.; Tillack, M. S.

doi:10.1016/s0920-3796(97)00116-6

Cited by 24 publications

(3 citation statements)

References 13 publications

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“…Therefore, we are proposing that passive measures be taken to remedy this problem. Two possible measures are either an in-vessel natural convection decay heat removal system similar to those proposed by References [69,70], or a passively activated valve that drains the Flinabe from the blanket into a tank that is passively cooled.…”

Section: Safetymentioning

confidence: 99%

A fusion reactor design with a liquid first wall and divertor

Nygren

Rognlien

Rensink

et al. 2004

Fusion Engineering and Design

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Within the magnetic fusion energy program in the US, a program called APEX is investigating the use of free flowing liquid surfaces to form the inner surface of the chamber around the plasma. As part of this work, the APEX Team has investigated several possible design implementations and developed a specific engineering concept for a fusion reactor with liquid walls. Our approach has been to utilize an already established design for a future fusion reactor, the ARIES-RS, for the basic chamber geometry and magnetic configuration and to replace the chamber technology in this design with liquid wall technology for a first wall and divertor and a blanket with adequate tritium breeding. This paper gives an overview of one design with a molten salt (a mixture of lithium, beryllium and sodium fluorides) forming the liquid surfaces and a ferritic steel for the structural material of the blanket. The design point is a reactor with 3840MW of fusion power of which 767MW is in the form of energetic particles (alpha power) and 3073MW is in the form of neutrons. The alpha plus auxiliary power total 909MW of which 430MW is radiated from the core mostly onto the first wall and the balance flows into the edge plasma and is distributed between the first wall and the divertor. In pursuing the application of liquid surfaces in APEX, the team has developed analytical tools that are significant achievements themselves and also pursued experiments on flowing liquids. This work is covered elsewhere, but the paper will also note several such areas to indicate the supporting science behind the design presented. Significant new work in modeling the plasma edge to understand the interaction of the plasma with the liquid walls is one example. Another is the incorporation of magneto-hydrodynamic (MHD) effects in fluid modeling and heat transfer.

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Section: Safetymentioning

confidence: 99%

A fusion reactor design with a liquid first wall and divertor

Nygren

Rognlien

Rensink

et al. 2004

Fusion Engineering and Design

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“…-Incorporate a LiPb heat removal loop (like that of ARIES-RS) using natural convection to transfer heat from the IB side to the OB side. 4 -Provide a rupture disk mechanism that will release the water vapor from the VV during LOCA/LOFA. -The water vapor released during LOCA/LOFA should be continuously collected, then condensed and returned back to the VV and LT shield.…”

Section: ------------------------------------------------------------mentioning

confidence: 99%

Loss of Coolant Accident and Loss of Flow Accident Analysis of the ARIES-AT Design

et al. 2001

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Loss of coolant accident (LOCA) and loss of flow accident (LOFA) analysis is performed for ARIES-AT, an advanced fusion power plant design (1000 MWe). ARIES-AT employs a high performance, high temperature blanket system. It uses the high temperature SiC/SiC for structural material and LiPb for coolant-breeder. Due to the large difference between the time scale of plasma shutdown and the coolant or power loss, it is assumed that the plasma is immediately quenched at the onset of the LOCA/LOFA and the chamber components' temperature begins to rise due to the decay heat generated. A 2-D transient finite element model is established to examine the thermal behavior of the in-vessel components to determine the maximum temperature reached, the time, and duration of the peak. The model is axisymmetric in (r-z) around the reactor axis to show the details of temperature distribution in the vertical direction. The vacuum vessel is assumed adiabatic in the inboard side and radiates to the maintenance port located on the outboard side. The maximum temperature of steel in the reactor is about (600°C-700°C) after about 4 days from the onset of the accident. The highest temperature in the reactor is in the divertor region and it reaches ≈1050°C after about 2-3 hours. The analysis indicates that the reactor does not need any special scheme for decay heat removal.

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“…Two possible passive measures to remedy this problem are either an in-vessel natural convection decay heat removal system similar to those proposed by Refs. [57,58], or a passively activated valve that drains the Flinabe from the blanket into a tank that is passively cooled.…”

Section: Safetymentioning

confidence: 99%

A fusion chamber design with a liquid first wall and divertor

Nygren

Sze²,

Nelson³

et al.

20th IEEE/NPSS Symposium onFusion Engineering, 2003.

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The APEX study is investigating the use of free flowing liquid surfaces to form the inner surface of the chamber around a fusion plasma. We present a design for the chamber of a 3840MW fusion reactor based on the configuration for the chamber and magnets from ARIES-RS but with a fast flowing molten salt of mixed Be, Li and Na fluorides for the first wall and divertor and molten salt blanket with a ferritic steel structure. Our design analysis includes strong radiation from the core and edge plasma, (liquid) MHD effects on the weakly conducting molten salt, a recycling first wall stream that enables a high efficiency thermal conversion, and evaluations of breeding, neutronics, tritium recovery and safety. . I.

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ARIES-RS safety design and analysis

Cited by 24 publications

References 13 publications

A fusion reactor design with a liquid first wall and divertor

A fusion reactor design with a liquid first wall and divertor

Loss of Coolant Accident and Loss of Flow Accident Analysis of the ARIES-AT Design

A fusion chamber design with a liquid first wall and divertor

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