ACTYS-1-GO: A faster and accurate algorithm for multipoint nuclear activation calculations

Abstract This article reports a relatively fast and accurate algorithm to solve large sized nuclear activation problems in one single run. The present algorithm reads material definition and neutron flux spectra generated by transport codes for complex geometries and then performs activation calculation based on the common parameters of the problem. The mathematical and computational details of simultaneous multipoint activation problem are presented along with the solution strategies. The present algorithm speeds up such calculations by generating a common coefficient matrix for a compact subset of the problem, depending upon one or more radiological results expected from the analysis and then removing the sparsity of the cross-section matrix. The algorithm is implemented in a computer code named ‘ACTYS-1-GO’. All the above steps and the implementation details are summarized in this article. A detailed validation of the code is also presented. Computational performance comparison for fusion-relevant problems has been carried out with the sequential use of activation code FISPACT and ‘Fornax’ module of Attila computer code.

[1]  Chikara Konno,et al.  ITER Nuclear Analysis Strategy and Requirements , 2009 .

[2]  Andrew A. Davis,et al.  Benchmarking the MCR2S system for high-resolution activation dose analysis in ITER , 2010 .

[3]  R. A. Forrest,et al.  FISPACT-2007: User manual , 2007 .

[4]  Cleve B. Moler,et al.  Nineteen Dubious Ways to Compute the Exponential of a Matrix, Twenty-Five Years Later , 1978, SIAM Rev..

[5]  S. Zinkle,et al.  Structural materials for fission & fusion energy , 2009 .

[6]  V. Udintsev,et al.  Neutronics analysis for integration of ITER diagnostics port EP10 , 2016 .

[7]  Shawn D. Pautz,et al.  Discontinuous Finite Element SN Methods on Three-Dimensional Unstructured Grids , 2001 .

[8]  Massimo Zucchetti,et al.  Accidental and long-term safety assessment of fission and fusion power reactors , 1999 .

[9]  S. Dudarev,et al.  Neutron-induced dpa, transmutations, gas production, and helium embrittlement of fusion materials , 2013, 1311.5079.

[10]  Laila A. El-Guebaly,et al.  Evaluation of disposal, recycling and clearance scenarios for managing ARIES radwaste after plant decommissioning , 2007 .

[11]  P. Humrickhouse,et al.  ARIES-ACT1 Safety Design and Analysis , 2015 .

[12]  Ulrich Fischer,et al.  Rigorous mcnp based shutdown dose rate calculations: computational scheme, verification calculations and application to ITER , 2002 .

[13]  David A. Petti,et al.  Materials challenges for nuclear systems , 2010 .

[14]  Forschungszentrum Karlsruhe,et al.  Computational Methods, Tools, and Data for Nuclear Analyses of Fusion Technology Systems , 2006 .

[15]  Javier Sanz,et al.  Developments and needs in nuclear analysis of fusion technology , 2013 .

[16]  D. Henderson,et al.  Activation and Environmental Aspects of ARIES-ACT1 Power Plant , 2015 .

[17]  J. Cetnar.  General solution of Bateman equations for nuclear transmutations , 2006 .

[18]  A. G. Croff,et al.  ORIGEN2: a revised and updated version of the Oak Ridge isotope generation and depletion code , 1980 .

[19]  P. V. Subhash,et al.  Activation and Radioactive Waste Analysis for Survey X-Ray Crystal Spectrometer of ITER , 2017 .

[20]  Michael Loughlin,et al.  Activation analyses updating the ITER radioactive waste assessment , 2012 .

[21]  P. Kanth,et al.  Parent Isotopic and Elemental Contributing Factors to Minimize Nuclear Radiological Responses and Optimize Material Composition , 2017 .

[22]  M. Pusa,et al.  Computing the Matrix Exponential in Burnup Calculations , 2010 .

[23]  P. V. Subhash,et al.  Development and validation of ACTYS, an activation analysis code , 2017 .