- Titel
- Entwicklung einer Methode zur Pre-Aktivitäts- und Dosisleistungsberechnung von reaktornahen Bauteilen auf Basis von Neutronenfluenzverteilungen – EMPRADO
- Untertitel
- Teilprojekt A: Berechnung der Neutronenfluenzverteilung in reaktornahen Bauteilen und deren Validierung an Experimenten als Basis der Aktivitätsrechnungen
- Zitierfähige Url:
- https://nbn-resolving.org/urn:nbn:de:bsz:d120-qucosa2-945750
- Schriftenreihe
- Wissenschaftlich-technische Berichte / Helmholtz-Zentrum Dresden - Rossendorf / HZDR
- Bandnummer
- HZDR-133
- Erstveröffentlichung
- 2024
- Abstract (EN)
- On the basis of an exact power history and accurate geometric modelling, plant-specific neutron fluences were calculated for in each case a pre- and convoy unit of German nuclear power plant for reactor components and for concrete and structural elements close to the reactor. These neutron fluences are the basis for determining the generated activation of the construction materials during the power operation of the plant. The calculations were supported by an extensive measurement program in the last cycles of two plants, where neutron fluence values were determined ex-perimentally with the help of activation foils (monitors). A spectral analysis was possible by using different monitor materials. The monitors were measured by gam-ma spectrometry after sampling using a high-purity germanium (HP-Ge) detector. The comparison of the calculated and measured activities shows, with a few excep-tions, good to very good agreement between the values. This means that the real ratios of neutron radiation in the elements were calculated very well and the method and model can be used to determine the activity distribution. Due to the possibility of the accurate simulation of the resulting activities on the ba-sis of these 'best estimate' calculations, detailed planning of the decommissioning can already begin during the operation of the plant. It is not necessary to wait until extensive sampling after the shutdown. In addition, the accurate mathematical determination of the activity distribution in the components enables improved cut planning and thus minimization of the waste volume for the final storage. A further advantage would be that the necessary exper-imental activity determinations could be reduced to a few samples thanks to the supporting experiments and thereby validated neutron fluence calculations.
- Freie Schlagwörter (EN)
- neutron; fluence calculation; neutron fluence monitor; decommissioning; power water reactor
- URN Qucosa
- urn:nbn:de:bsz:d120-qucosa2-945750
- Veröffentlichungsdatum Qucosa
- 19.12.2024
- Dokumenttyp
- Bericht
- Sprache des Dokumentes
- Deutsch
- Lizenz / Rechtehinweis
CC BY 4.0