Fuel inventory of the iPWR Design-1 and Design-2

The amount of Fission Products (FP) in the core is one of the key parameters driving the progression and the radiological consequences of a hypothetical postulated Severe Accident (SA) in a Nuclear Power Plant (NPP). The larger the mass of FPs loaded, the larger is the decay power, which triggers the accident after the reactor scram. Having this in mind, the effect of the employment of different amount of FPs should be considered in the analysis of a hypothetical SA. The current report focusses on the evaluation of the fuel inventory at different burn-up states in the integral Pressurized Water Reactor (iPWR) Design-1 and Design-2 in the framework of the work activities of the Task 2.3 of the WP2 (SCENARIOS) of the SASPAM-SA project. With this goal, depletion calculations have been performed at the Karlsruhe Institute of Technology (KIT, Germany) by means of the CASMO5 lattice physics code [1], developed by Studsvik Scandpower, for a representative fuel assembly of the iPWR Design-1 and Design-2 in order to assess a database of fuel inventories to be employed in the activities of the SASPAM-SA project. The calculation assumptions as well as the results of such evaluations are reported and discussed in the present document.

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Publication Details

Journal
Zenodo (CERN European Organization for Nuclear Research)
Published
2024-11-07
DOI
https://doi.org/10.5281/zenodo.14052163
Citations
1
Primary Topic
Nuclear Materials and Properties
Type
article
Field-Weighted Citation Impact
0.12
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Fuel inventory of the iPWR Design-1 and Design-2

1 citations
Zenodo (CERN European Organization for Nuclear Research)
Nuclear Materials and Properties
0.12
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Fuel inventory of the iPWR Design-1 and Design-2

article en
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Abstract

The amount of Fission Products (FP) in the core is one of the key parameters driving the progression and the radiological consequences of a hypothetical postulated Severe Accident (SA) in a Nuclear Power Plant (NPP). The larger the mass of FPs loaded, the larger is the decay power, which triggers the accident after the reactor scram. Having this in mind, the effect of the employment of different amount of FPs should be considered in the analysis of a hypothetical SA. The current report focusses on the evaluation of the fuel inventory at different burn-up states in the integral Pressurized Water Reactor (iPWR) Design-1 and Design-2 in the framework of the work activities of the Task 2.3 of the WP2 (SCENARIOS) of the SASPAM-SA project. With this goal, depletion calculations have been performed at the Karlsruhe Institute of Technology (KIT, Germany) by means of the CASMO5 lattice physics code [1], developed by Studsvik Scandpower, for a representative fuel assembly of the iPWR Design-1 and Design-2 in order to assess a database of fuel inventories to be employed in the activities of the SASPAM-SA project. The calculation assumptions as well as the results of such evaluations are reported and discussed in the present document.

Zenodo (CERN European Organization for Nuclear Research)
Karlsruhe Institute of Technology (DE)
Openalex Percentile: Top 56%
Nuclear Materials and Properties
0.12
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