Development of a thick CdTe detector for BNCT–SPECT
- 1. Division of Electrical, Electronic and Information Engineering, Graduate School of Engineering, Osaka University, Yamada-oka 2-1, Suita, Osaka 565-0871 (Japan)
- 2. Department of Oral and Maxillofacial Surgery II, Graduate School of Dentistry, Osaka University, Yamada-oka 1-8, Suita, Osaka 565-0871 (Japan)
Description
As well known, it is difficult to know the exact treatment effect of boron neutron capture therapy (BNCT). It depends on the irradiation time, which is changed rather flexibly. At present, it is once fixed before BNCT. Then the actual stopping time is adjusted during BNCT by some means like activation foils. The author's group hence started development of a single-photon emission computed tomography (SPECT) system for BNCT to know the effect of BNCT in real time. By adopting a side surface (1×2 mm2) of a CdTe detector (1×2×20 mm3) as radiation entrance window, acceptable spatial resolution and high detection efficiency were simultaneously achieved. Also in about 30 min acceptable number of counts for 478 keV gamma-rays could be expected. In addition, employing a Schottky type detector the energy resolution could be improved. Discrimination of 478 keV and annihilation gamma-rays would thus be successfully made. In the next phase, it is planned to design and develop an array type detector to be implemented in the BNCT–SPECT system. - Highlights: ► BNCT needs treatment effect information, but very difficult to measure. ► CdTe device is employed to develop BNCT–SPECT to know 3-D BNCT effect. ► Using side surface of CdTe wafer as radiation entrance SPECT performance is enhanced. ► In 30 min enough count around 1000 can be obtained for 478 keV gamma-rays. ► Array type CdTe detector is now designed for prototype BNCT–SPECT.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.apradiso.2011.05.014Additional details
Identifiers
- DOI
- 10.1016/j.apradiso.2011.05.014;
- PII
- S0969-8043(11)00299-5;
Publishing Information
- Journal Title
- Applied Radiation and Isotopes
- Journal Volume
- 69
- Journal Issue
- 12
- Journal Page Range
- p. 1706-1709
- ISSN
- 0969-8043
- CODEN
- ARISEF
Conference
- Title
- 14. international conference on neutron capture therapy
- Dates
- 25-29 Oct 2010
- Place
- Buenos Aires (Argentina)
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 43071808
- Subject category
- S07: ISOTOPES AND RADIATION SOURCES;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ANNIHILATION; CDTE SEMICONDUCTOR DETECTORS; EFFICIENCY; ENERGY RESOLUTION; GAMMA RADIATION; IRRADIATION; KEV RANGE 100-1000; NEUTRON CAPTURE THERAPY; SINGLE PHOTON EMISSION COMPUTED TOMOGRAPHY; SPATIAL RESOLUTION; SURFACES
- Descriptors DEC
- COMPUTERIZED TOMOGRAPHY; DIAGNOSTIC TECHNIQUES; ELECTROMAGNETIC RADIATION; EMISSION COMPUTED TOMOGRAPHY; ENERGY RANGE; INTERACTIONS; IONIZING RADIATIONS; KEV RANGE; MEASURING INSTRUMENTS; MEDICINE; NEUTRON THERAPY; NUCLEAR MEDICINE; PARTICLE INTERACTIONS; RADIATION DETECTORS; RADIATIONS; RADIOLOGY; RADIOTHERAPY; RESOLUTION; SEMICONDUCTOR DETECTORS; THERAPY; TOMOGRAPHY
Optional Information
- Copyright
- Copyright (c) 2011 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.