Safety Evaluation of the EVOLVE Blanket Concept

Merrill, B.J.; Marshall, Theron D.; Khater, H. Y.; Malang, S.; Wong, C.P.C.

doi:10.13182/fst03-a363

Cited by 3 publications

(3 citation statements)

References 8 publications

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“…Analysis of W releases for the EVOLVE design [26] found that the dosage at site boundary was 0.13 Sv/kg for stacked releases of W under worst case atmospheric conditions, and about 2% of the tungsten might be released to the environment without filtering. After two years of dust accumulation, this could lead to an offsite dosage of 1.25 Sv, which is well above the no evacuation limit of .01 Sv.…”

Section: Potential Safety Consequences Of Tungsten Dustmentioning

confidence: 99%

Implications of convective scrape-off layer transport for fusion reactors with solid and liquid walls

Kotschenreuther

Rognlien

Valanju

2004

Fusion Engineering and Design

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Recent experimental observations in tokamaks indicate enhanced convection of plasma blobs toward the main chamber wall. Potential implications of these observations for reactors are examined here. Two dimensional plasma edge calculations are performed with UEDGE, including convective transport consistent with present experiments. This is coupled to a kinetic neutral calculation using the code NUT, to compute the hot neutral flux to the wall. The inclusion of convection increases sputtering of the wall by roughly an order of magnitude. For tungsten walls, erosion (neglecting re-deposition) is estimated to be ~0.6 mm per year. Plasma contamination could be serious for high Z walls of W or Sn, and might preclude ignition (based on empirical screening estimates). Low Z liquid materials offer much better prospects for acceptable plasma contamination. Rough estimates of dust generation from such erosion rates imply significant safety issues. Plasma transport via blobs can also significantly modify models of impurity redeposition.

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Section: Potential Safety Consequences Of Tungsten Dustmentioning

confidence: 99%

Implications of convective scrape-off layer transport for fusion reactors with solid and liquid walls

Kotschenreuther

Rognlien

Valanju

2004

Fusion Engineering and Design

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“…Liquid lithium was recently proposed for the laser inertial fusion engine (LIFE) lithium self-cooled blanket concept [125]. It has also been proposed in past design studies [126,127]. Lithium is a very chemically reactive metal.…”

Section: Tritium Breeding Materialsmentioning

confidence: 99%

Materials-related issues in the safety and licensing of nuclear fusion facilities

et al. 2017

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Fusion power holds the promise of electricity production with a high degree of safety and low environmental impact. Favourable characteristics of fusion as an energy source provide the potential for this very good safety and environmental performance. But to fully realize the potential, attention must be paid in the design of a demonstration fusion power plant (DEMO) or a commercial power plant to minimize the radiological hazards. These hazards arise principally from the inventory of tritium and from materials that become activated by neutrons from the plasma. The confinement of these radioactive substances, and prevention of radiation exposure, are the primary goals of the safety approach for fusion, in order to minimize the potential for harm to personnel, the public, and the environment. The safety functions that are implemented in the design to achieve these goals are dependent on the performance of a range of materials. Degradation of the properties of materials can lead to challenges to key safety functions such as confinement. In this paper the principal types of material that have some role in safety are recalled. These either represent a potential source of hazard or contribute to the amelioration of hazards; in each case the related issues are reviewed. The resolution of these issues lead, in some instances, to requirements on materials specifications or to limits on their performance.

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“…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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Safety Evaluation of the EVOLVE Blanket Concept

Cited by 3 publications

References 8 publications

Implications of convective scrape-off layer transport for fusion reactors with solid and liquid walls

Implications of convective scrape-off layer transport for fusion reactors with solid and liquid walls

Materials-related issues in the safety and licensing of nuclear fusion facilities

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

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