ACTYS-ASG, tool for coupling ACTYS-1-GO with ATTILA

Kanth, Priti; Subhash, P.V.

doi:10.1016/j.fusengdes.2018.02.092

Cited by 4 publications

(5 citation statements)

References 17 publications

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“…As discussed in section 2, ECF/ICF gives a direct correlation between the radiological quantities and the elements/isotopes present in the initial material composition. To demonstrate the capabilities and the usefulness of the tool, 'ITER Shutdown Dose Rate Benchmarking problem' is used as the reference model [26,28]. Using default setting mentioned in section 3, the composition of SS316 is optimized and the radiological quantities with the optimized composition are compared with that of original material.…”

Section: Effectiveness Of Materials Optimization Using Multi-paramete...mentioning

confidence: 99%

“…The flux and energy spectrum for ITER-shutdown benchmark model is evaluated using deterministic neutron transport code, ATTILA details of which can be found in [26,35,36]. A detailed description of the problem is given in [28], a brief description for immediate reference is given below.…”

Section: Effectiveness Of Materials Optimization Using Multi-paramete...mentioning

confidence: 99%

“…The Quarter geometry of the model for ITER shutdown dose rate benchmark study ( [28]) that is used for flux generation and activation calculation. In our earlier work, evaluation of the neutron flux using ATTILA has been carried out for a different purpose and is detailed in [26]. The model is divided into more than 50 thousand fine meshes and a biased quadrature with a S N order of 32 is used in the Attila transport calculations.…”

Section: Effectiveness Of Materials Optimization Using Multi-paramete...mentioning

confidence: 99%

“…The reduced matrix generated yields radiological quantities with more than 99% accuracy and reduces the runtime by 98% in comparison to sequential execution of single point codes ACTYS and FISPACT. The code is further coupled with radiation transport code ATTILA under the R2S scheme to achieve fast SDDR calculations [26]. A fundamental method for quantifying isotopic nuclear response to the overall material response is developed [27].…”

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

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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: Effectiveness Of Materials Optimization Using Multi-paramete...mentioning

confidence: 99%

Section: Effectiveness Of Materials Optimization Using Multi-paramete...mentioning

confidence: 99%

Section: Effectiveness Of Materials Optimization Using Multi-paramete...mentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

See 2 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

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show abstract

“…Next, we consider an analytic function f and the Krylov subspaces  m (A, y) and  m (A H , z), the bases V m and W m , and the corresponding Hessenberg matrices G m and H m satisfying the relations ( 15) and ( 16). Motivated by (58), we estimate the error of the Arnoldi approximation (18) of the Fréchet derivative L f (A, 𝜂yz H ) by a heuristic estimate…”

Section: A Posteriori Error Estimatesmentioning

confidence: 99%

Computing low‐rank approximations of the Fréchet derivative of a matrix function using Krylov subspace methods

Kandolf

Koskela

Relton

et al. 2021

Numerical Linear Algebra App

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The Fréchet derivative L f (A, E) of the matrix function f (A) plays an important role in many different applications, including condition number estimation and network analysis. We present several different Krylov subspace methods for computing low-rank approximations of L f (A, E) when the direction term E is of rank one (which can easily be extended to general low rank). We analyze the convergence of the resulting methods both in the Hermitian and non-Hermitian case. In a number of numerical tests, both including matrices from benchmark collections and from real-world applications, we demonstrate and compare the accuracy and efficiency of the proposed methods.

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Development of shutdown dose rate calculation code based on cosRMC and application to benchmark analysis

Zhang

Liu

et al. 2021

Fusion Engineering and Design

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ACTYS-ASG, tool for coupling ACTYS-1-GO with ATTILA

Cited by 4 publications

References 17 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

Computing low‐rank approximations of the Fréchet derivative of a matrix function using Krylov subspace methods

Development of shutdown dose rate calculation code based on cosRMC and application to benchmark analysis

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