| Issue |
EPJ Web Conf.
Volume 308, 2024
ISRD 17 – International Symposium on Reactor Dosimetry (Part II)
|
|
|---|---|---|
| Article Number | 02005 | |
| Number of page(s) | 8 | |
| Section | Calculational Methods | |
| DOI | https://doi.org/10.1051/epjconf/202430802005 | |
| Published online | 11 November 2024 | |
https://doi.org/10.1051/epjconf/202430802005
Further development, validation and verification of the Monte-Carlo code TRAMO on ex-vessel experiments of the Greifswald NPP
1 Technische Universität Dresden, 01069 Dresden, Germany
2 Helmholtz-Zentrum Dresden-Rossendorf, Bautzner Landstr. 400, 01328 Dresden, Germany
* Corresponding author: s.baier@hzdr.de
Published online: 11 November 2024
TRAMO is a Monte Carlo code which is specially designed for geometries of nuclear power plants. In recent years, TRAMO has undergone a number of technical developments. In addition to the conversion to modern Fortran, standardized models for VVER-440 and VVER-1000 for the evaluation of monitor experiments on the surface of the reactor pressure vessel were developed, and the corresponding pre- and post-processing was automated. The new TRAMO version is continuously validated and verified. Here we present comparisons with experimental data from unit 1 of the Greifswald nuclear power plant and with MCNP calculations. Earlier calculations with TRAMO showed good agreements in the middle region of the reactor core, but significant deviations outside. A possible explanation is the wrong documentation of the experimental data – especially the heights of the monitors. Assuming a downward shift of the monitor positions by about 24cm, experimental and calculated data show very good agreement.
© The Authors, published by EDP Sciences, 2024
This is an Open Access article distributed under the terms of the Creative Commons Attribution License 4.0, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.
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