Ústav technické a experimentální fyziky Institute of Experimental and Applied Physics

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
DOIDOI
10.1016/j.apradiso.2020.109395
Časopis / citaceJournal / citation
Applied Radiation and Isotopes. 2020, 166 ISSN 0969-8043.
RokYear
2020
JazykLanguage
eng
WoSWoS
000589093400059
ScopusScopus
2-s2.0-85090360997
RIVRIV
RIV/68407700:21670/20:00342793!RIV21-TA0-21670___
ProjektProject
ECHORD Plus Plus: RadioRoSo ExperimentECHORD Plus Plus / RadioRoSo: Radioactive Waste Robotic Sorter; Centrum aplikované kybernetiky 3Centre for Applied Cybernetics 3

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.