DocumentCode :
3144770
Title :
Simulation of radiation monitoring system for dry storage casks
Author :
Ivanov, Alexander ; Pedash, V. ; Kolbasin, V.
Author_Institution :
Inst. for Scintillator Mater., Kharkiv, Ukraine
fYear :
2013
fDate :
23-27 June 2013
Firstpage :
1
Lastpage :
3
Abstract :
The simulation has been carried out of the radiation monitoring systems for dry storage casks of spent nuclear fuel (SNF). Two types of systems have been tested: system based on gamma imaging and neutron imaging. The main objective of the work is finding optimal design for integrity check of the outer shell of the cask (cracks in the concrete walls, welds sealing, etc.). The secondary objectives are assessing activity of the fuel and obtaining tomographic sections of the cask. It is supposed that the monitoring system consists of a gamma/neutron imager mounted on a gantry for radial and vertical movement to scan the surface of the cask. It has been shown that coded aperture gamma telescope based on continuous scintillation CsI(Na) crystal or pixelated CZT detector can be used for flaw detection in concrete walls. The estimated time of inspection is several days for a cask of 3.4meter diameter and a length of 5.8 meters. The best result achieved is the detection of defects of ~10 cm size. The further optimization of the detectors, however, can reduce this value to several centimeters. Neutron imager has worse performance, and can be used as an auxiliary detector. The paper presents the results of simulations and discusses the possible implementation of the detectors.
Keywords :
flaw detection; gamma-ray detection; neutron detection; optimisation; radiation monitoring; radioactive waste storage; semiconductor counters; solid scintillation detectors; auxiliary detector; coded aperture gamma telescope; concrete walls; continuous scintillation CsI(Na) crystal; cracks; dry storage casks; flaw detection; gamma imaging; integrity check; neutron imaging; optimal design; pixelated CZT detector; radial movement; radiation monitoring system; size 3.4 m; size 5.8 m; spent nuclear fuel; tomographic sections; vertical movement; weld sealing; Assembly; Concrete; Detectors; Fuels; Monitoring; Neutrons; Tomography; GEANT4; dry storage cask; spent nuclear fuel;
fLanguage :
English
Publisher :
ieee
Conference_Titel :
Advancements in Nuclear Instrumentation Measurement Methods and their Applications (ANIMMA), 2013 3rd International Conference on
Conference_Location :
Marseille
Print_ISBN :
978-1-4799-1046-5
Type :
conf
DOI :
10.1109/ANIMMA.2013.6727933
Filename :
6727933
Link To Document :
بازگشت