Development and validation of ACTYS, an activation analysis code

Tadepalli, Sai Chaitanya; Kanth, Priti; Indauliya, Gunjan; Saikia, Ishwita; Deshpande, Shantanu; Subhash, P.V.

doi:10.1016/j.anucene.2017.04.016

Cited by 12 publications

(5 citation statements)

References 13 publications

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“…The nuclear activation problem is governed by first order linear differential equation, known as the Bateman equation [29]. In a homogeneous, infinite and infinitely dilute material, the time evolution rate of nuclides can be written as [24,30]:…”

Section: Materials Optimization Formalization Based On Single Neutron...mentioning

confidence: 99%

“…Contact dose rate at the surface of a semi-infinite uniform volume source calculated by formula [24]:…”

Section: Materials Optimization Formalization Based On Single Neutron...mentioning

confidence: 99%

“…where µ m = mi M µ i , for details refer to article: [24]. Similar to equation ( 6), contact dose rate can be written as…”

Section: Materials Optimization Formalization Based On Single Neutron...mentioning

confidence: 99%

“…ACTYS-1-GO is a multipoint activation code that uses a robust algorithm to make it suitable for simultaneous multiple point calculations using linear chain solver for a given flux. The various techniques for single point and multipoint activation solver are detailed in [24,25]. In multipoint calculations, the entire nuclear device is divided into small sections called meshes.…”

Section: Implementation Of Optimization Procedures In Actys-1-gomentioning

confidence: 99%

“…For this purpose, a project is being carried out at ITER-India, Institute for Plasma Research to develop suitable indigenous numerical tools for such studies [23]. As a first step, a singlepoint nuclear activation code 'ACTYS' has been developed [24]. After that, a fast and accurate algorithm for multipoint activation calculation is developed and is implemented in a computer code named 'ACTYS-1-GO' [25].…”

Section: Introductionmentioning

confidence: 99%

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Composition optimization strategy based on multiple radiological responses for materials in spatially and temporally varying neutron fields

Kanth¹,

Tadepalli²,

Subhash³

2018

Nucl. Fusion

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Structural materials present in and around any fusion device will face stringent conditions due to the high-energy and high-flux neutrons emitted from the fusion plasma. These neutrons can cause induced radioactivity, gas production, energetic knock out atoms, atomic displacement and decay heat in these materials. This would have a significant life-limiting impact on the materials and would also cause biological hazards and radioactive waste. Hence designing low activation materials for fusion devices is warranted. This paper presents a novel tool for quantification of radiological responses in terms of the elements present in the initial material composition. Such a framework would help in the identification and optimization of the fraction of most dangerous elements/isotopes from the material composition. In practical scenarios, the material encounters a large spatial and temporal variation of neutron fluxes. This problem has been effectively treated in the present work using a multi-parameter optimization scheme. The scheme optimizes the material composition (elemental or isotopic) based on various nuclear responses and there spatial and temporal variations within the user-defined constraints. This scheme is further included in the multi-point activation code ACTYS-1-GO. The tool provides a comprehensive picture of the material response during neutron irradiation and after shutdown, enabling the assessment of structural integrity of components in a fusion device. As an aide to the material optimization process, this paper also introduces a visual representation of the evaluated information like quantification of radiological responses produced by the parent elements/isotopes in a material. This has been implemented through a series of spectrum independent and spectrum-dependent diagrams called the radiation response diagrams. These diagrams show the variation of contributing parents toward the radiological responses as a function of cooling time. Such a graph could be very useful as a first approximation for material design.

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Section: Materials Optimization Formalization Based On Single Neutron...mentioning

confidence: 99%

“…Contact dose rate at the surface of a semi-infinite uniform volume source calculated by formula [24]:…”

Section: Materials Optimization Formalization Based On Single Neutron...mentioning

confidence: 99%

“…where µ m = mi M µ i , for details refer to article: [24]. Similar to equation ( 6), contact dose rate can be written as…”

Section: Materials Optimization Formalization Based On Single Neutron...mentioning

confidence: 99%

Section: Implementation Of Optimization Procedures In Actys-1-gomentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

See 3 more Smart Citations

Composition optimization strategy based on multiple radiological responses for materials in spatially and temporally varying neutron fields

Kanth¹,

Tadepalli²,

Subhash³

2018

Nucl. Fusion

Self Cite

View full text Add to dashboard Cite

show abstract

Simplified recursive relations for the derivatives of Bateman linear chain solution and their application to sensitivity and multi-point analysis

Tadepalli

Subhash

2018

Annals of Nuclear Energy

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Removing singularities in the Bateman radioactive transformation equations using partial fraction decomposition

Malovytsia

2023

Annals of Nuclear Energy

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Development and validation of ACTYS, an activation analysis code

Cited by 12 publications

References 13 publications

Composition optimization strategy based on multiple radiological responses for materials in spatially and temporally varying neutron fields

Composition optimization strategy based on multiple radiological responses for materials in spatially and temporally varying neutron fields

Simplified recursive relations for the derivatives of Bateman linear chain solution and their application to sensitivity and multi-point analysis

Removing singularities in the Bateman radioactive transformation equations using partial fraction decomposition

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