Safety and Environment Assessment of ARIES-AT

Petti, David A.; Merrill, B.J.; Moore, Richard L.; Longhurst, G.R.; El-Guebaly, L.; Mogahed, E.A.; Henderson, D.; Wilson, Paul P. H.; Abdou, A.

doi:10.13182/fst01-a11963277

Cited by 7 publications

(2 citation statements)

References 17 publications

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“…Previous safety studies show that the radioactive isotopes of Pb-17Li that are a safety concern are Po-210 and Hg-203 [8]. Neutronics calculations have been performed for the DCLL TBM with the ONEDANT module of the DANTSYS 3.0 discrete ordinates particle transport code system [9].…”

Section: Source Termsmentioning

confidence: 99%

Safety analysis of the US dual coolant liquid lead–lithium ITER test blanket module

Merrill¹,

Reyes²,

Sawan³

et al. 2007

Nucl. Fusion

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The US is proposing a prototype of a dual coolant liquid lead-lithium DEMO blanket concept for testing in the International Thermonuclear Experimental Reactor (ITER) as an ITER test blanket module (TBM). Because safety considerations are an integral part of the design process to ensure that this TBM does not adversely impact the safety of ITER, a safety assessment has been conducted for this TBM and its ancillary systems as requested by the ITER project. Four events were selected by the ITER international team (IT) to address specific reactor safety concerns, such as vaccum vessel (VV) pressurization, confinement building pressure build-up, TBM decay heat removal capability, tritium and activation products release from the TBM system and hydrogen and heat production from chemical reactions. This paper summarizes the results of this safety assessment conducted with the MELCOR computer code.

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Section: Source Termsmentioning

confidence: 99%

Safety analysis of the US dual coolant liquid lead–lithium ITER test blanket module

Merrill¹,

Reyes²,

Sawan³

et al. 2007

Nucl. Fusion

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show abstract

“…Our work over the past 5 years has focused on improving these safety codes to support the safety assessments of the ARIES, APEX and ALPS designs by accommodating different materials, coolants and geometric configurations [7][8][9][10]. In addition, we have continued to verify and validate (V&V) our fusion safety codes by collaborating in international code benchmarking experiments being performed by Japan and Europe.…”

Section: Fusion Safety Computer Codesmentioning

confidence: 99%

Recent accomplishments and future directions in the US Fusion Safety and Environmental Program

et al. 2007

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The US Fusion Program has long recognized that the safety and environmental (S&E) potential of fusion can be attained by prudent materials selection, judicious design choices and integration of safety requirements into the design of the facility. To achieve this goal, S&E research is focused on understanding the behaviour of the largest sources of radioactive and hazardous materials in a fusion facility, understanding how energy sources in a fusion facility could mobilize those materials, developing integrated state-of-the-art S&E computer codes and risk tools for safety assessment and evaluating S&E issues associated with current fusion designs. In this paper, recent accomplishments are reviewed and future directions outlined.

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Preliminary environmental radiation considerations for CFETR

Nie

Jiang

et al. 2019

Fusion Engineering and Design

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Safety and Environment Assessment of ARIES-AT

Cited by 7 publications

References 17 publications

Safety analysis of the US dual coolant liquid lead–lithium ITER test blanket module

Safety analysis of the US dual coolant liquid lead–lithium ITER test blanket module

Recent accomplishments and future directions in the US Fusion Safety and Environmental Program

Preliminary environmental radiation considerations for CFETR

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