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R.E. Fairhurst-Agosta, T. Kozlowski, "Demonstration of Decay Heat Calculations using the MCNP-ORIGEN Activation Automation Tool", in B.H.V. Topping, P. Iványi, (Editors), "Proceedings of the Eleventh International Conference on Engineering Computational Technology", Civil-Comp Press, Edinburgh, UK, Online volume: CCC 2, Paper 15.1, 2022, doi:10.4203/ccc.2.15.1

Keywords: safety, decay, heat, MCNP, ORIGEN, MOAA.

Abstract

This work targets mainly experiment safety analyses for research nuclear reactors. The safety analyses evince that accidents do not undermine the experiment integrity, which could lead to a radioactive material release. After a reactor shutdown, the radioactive materials continue to decay and release energy. Nuclear safety analyses require the estimation of this released energy. The accurate assessment of this released energy allows to better determine the heat removal requirements and ensure the effective experiment cooldown. The main objective of this summary is to introduce a module capable of calculating the heat production in an experiment due to decay heating. For the calculation, the module relies on the MCNP-ORIGEN Activation Automation (MOAA) tool. This paper introduces the decay heat calculation module, explains its workflow, and showcases its capabilities by conducting a simple nuclear engineering exercise.

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Front Page Browse CCC CCP CSETS CTR IJRT Other Authors Search Purchase Guide FAQ Contact us	Civil-Comp Conferences ISSN 2753-3239 CCC: 2 PROCEEDINGS OF THE ELEVENTH INTERNATIONAL CONFERENCE ON ENGINEERING COMPUTATIONAL TECHNOLOGY Edited by: B.H.V. Topping and P. Iványi Paper 15.1 Demonstration of Decay Heat Calculations using the MCNP-ORIGEN Activation Automation Tool R.E. Fairhurst-Agosta and T. Kozlowski Dept. of Nuclear, Plasma, and Radiological Engineering, University of Illinois at Urbana-Champaign, Urbana, United States doi:10.4203/ccc.2.15.1 Full Bibliographic Reference for this paper R.E. Fairhurst-Agosta, T. Kozlowski, "Demonstration of Decay Heat Calculations using the MCNP-ORIGEN Activation Automation Tool", in B.H.V. Topping, P. Iványi, (Editors), "Proceedings of the Eleventh International Conference on Engineering Computational Technology", Civil-Comp Press, Edinburgh, UK, Online volume: CCC 2, Paper 15.1, 2022, doi:10.4203/ccc.2.15.1 Keywords: safety, decay, heat, MCNP, ORIGEN, MOAA. Abstract This work targets mainly experiment safety analyses for research nuclear reactors. The safety analyses evince that accidents do not undermine the experiment integrity, which could lead to a radioactive material release. After a reactor shutdown, the radioactive materials continue to decay and release energy. Nuclear safety analyses require the estimation of this released energy. The accurate assessment of this released energy allows to better determine the heat removal requirements and ensure the effective experiment cooldown. The main objective of this summary is to introduce a module capable of calculating the heat production in an experiment due to decay heating. For the calculation, the module relies on the MCNP-ORIGEN Activation Automation (MOAA) tool. This paper introduces the decay heat calculation module, explains its workflow, and showcases its capabilities by conducting a simple nuclear engineering exercise. download the full-text of this paper (PDF, 6 pages, 328 Kb) go to the previous paper go to the next paper return to the table of contents return to the volume description
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