The use of a CZT detector with robotic systems
- NázevTitle
- The use of a CZT detector with robotic systemsThe use of a CZT detector with robotic systems
- Druh výsledkuResult type
- Článek v časopiseJournal article
- AutořiAuthors
- A. Selivanova, J. Hůlka, D. Seifert, V. Hlaváč, P. Krsek, V. Smutný, L. Wagner, J. Voltr, P. Rubovič, I. Češpírová, L. Gryc
- Klíčová slovaKeywords
- MCNP, CdZnTe, Minimum detectable activity, Shielding, Waste, Monte Carlo, simulation, Dual-arm robot, Orphan Source
- DOIDOI
- 10.1016/j.apradiso.2020.109395
- Časopis / citaceJournal / citation
- Applied Radiation and Isotopes 166, 109395 (2020) · ISSN 0969-8043
- RokYear
- 2020
- JazykLanguage
- eng
- ZáznamyRecords
- ProjektProject
- ECHORD Plus Plus: RadioRoSo ExperimentECHORD Plus Plus / RadioRoSo: Radioactive Waste Robotic Sorter; Centrum aplikované kybernetiky 3Centre for Applied Cybernetics 3
- CitovánoCited by
- 10 (OpenAlex)
- Citace ke staženíDownload citation
- TXT · BibTeX
AbstraktAbstract
This work is focused on the use of a CZT detector for a radiation mapping with an industrial robotic arm. Measurements were carried out within the RadioRoSo experiment (Radioactive Waste Robotic Sorter), under the umbrella of EU FP7 project ECHORD++. In tests with a dual-arm robot and standard point sources of 137Cs and 60Co, a Magnox waste was mimicked. Thereafter, for relevant measurement geometries and selected shielding materials, full energy peak efficiencies were calculated using the MCNP transport code. Simulated FEP efficiency values were used for minimum detectable activity assessments for expected measurement conditions. Obtained results would be also applicable for cases of shielded lost/orphan point-like sources.
This work is focused on the use of a CZT detector for a radiation mapping with an industrial robotic arm. Measurements were carried out within the RadioRoSo experiment (Radioactive Waste Robotic Sorter), under the umbrella of EU FP7 project ECHORD++. In tests with a dual-arm robot and standard point sources of 137Cs and 60Co, a Magnox waste was mimicked. Thereafter, for relevant measurement geometries and selected shielding materials, full energy peak efficiencies were calculated using the MCNP transport code. Simulated FEP efficiency values were used for minimum detectable activity assessments for expected measurement conditions. Obtained results would be also applicable for cases of shielded lost/orphan point-like sources.