CR-39 detector based thermal neutron flux measurements, in the photo neutron project

被引:9
|
作者
Mameli, A. [2 ]
Greco, F. [2 ]
Fidanzio, A. [2 ]
Fusco, V.
Cilla, S. [3 ]
D'Onofrio, G. [3 ]
Grimaldi, L. [3 ]
Augelli, B. G. [3 ]
Giannini, G. [4 ,5 ]
Bevilacqua, R. [4 ,5 ]
Totaro, P. [4 ,5 ]
Tommasino, L.
Azario, L. [1 ]
Piermattei, A. [1 ]
机构
[1] Univ Cattolica Sacro Cuore, Ist Fis, Rome, Italy
[2] Univ Cattolica Sacro Cuore, UO Fis Sanit Policlin A Gemelli, Rome, Italy
[3] Univ Cattolica Sacro Cuore, UO Fis Sanit, Ctr Ric & Formaz Ad Alta Tecnol Sci Biomed, Campobasso, Italy
[4] Univ Trieste, Dipartimento Fis, Trieste, Italy
[5] Ist Nazl Fis Nucl, Sez Trieste, Trieste, Italy
关键词
neutron; CR-39; BNCT;
D O I
10.1016/j.nimb.2008.05.122
中图分类号
TH7 [仪器、仪表];
学科分类号
0804 ; 080401 ; 081102 ;
摘要
PhoNeS (photo neutron source) is a project aimed at the production and moderation of neutrons by exploiting high energy linear accelerators, currently used in radiotherapy. A feasibility study has been carried out with the scope in mind to use the high energy photon beams from these accelerators for the production of neutrons suitable for boron neutron capture therapy (BNCT). Within these investigations, it was necessary to carry out preliminary measurements of the thermal neutron component of neutron spectra, produced by the photo-conversion of X-ray radiotherapy beams supplied by three LinAcs: 15 MV, 18 MV and 23 MV. To this end, a simple passive thermal neutron detector has been used which consists of a CR-39 track detector facing a new type of boron-loaded radiator. Once calibrated, this passive detector has been used for the measurement of both the thermal neutron component and the cadmium ratio of different neutron spectra. In addition, bubble detectors with a response highly sensitive to thermal neutrons have also been used. Both thermal neutron detectors are simple to use, very compact and totally insensitive to low-ionizing radiation such as electrons and X-rays. The resultant thermal neutron flux was above 10(6) n/cm(2) s and the cadmium ratio was no greater than 15 for the first attempt of photo-conversion of X-ray radiotherapy beams. (C) 2008 Elsevier B.V. All rights reserved.
引用
收藏
页码:3656 / 3660
页数:5
相关论文
共 50 条
  • [1] A CR-39 based thermal neutron dosimeter
    Ahmad, N
    Matiullah
    Kenawy, MA
    RADIATION MEASUREMENTS, 1997, 28 (1-6) : 413 - 414
  • [2] CR-39 based thermal neutron dosimeter
    Cent for Nuclear Studies, Islamabad, Pakistan
    Radiat Meas, 1-6 (413-414):
  • [3] CR-39 USED AS A DETECTOR IN A NEUTRON DOSIMETER
    VAREILLE, JC
    DECOSSAS, JL
    SADAKA, S
    TEYSSIER, JL
    NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION B-BEAM INTERACTIONS WITH MATERIALS AND ATOMS, 1986, 17 (03): : 280 - 284
  • [4] THE DEVELOPMENT OF NEUTRON DOSIMETER USING CR-39 DETECTOR
    ELKHATIB, AM
    ABOUELKHIER, AA
    FAWZY, MA
    ELCHENNAWI, SE
    RADIATION EFFECTS AND DEFECTS IN SOLIDS, 1994, 128 (04): : 319 - 325
  • [5] Computer simulation of the processes in a CR-39 neutron detector
    Lengar, I
    Skvarc, J
    Ilic, R
    RADIATION MEASUREMENTS, 2003, 36 (1-6) : 115 - 118
  • [6] AN IMPROVED CR-39 DETECTOR MATERIAL WITH LOW BACKGROUND FOR ALPHA AND NEUTRON MEASUREMENTS
    GUHR, A
    SARENIO, O
    LASSARY, D
    RADIATION PROTECTION DOSIMETRY, 1990, 34 (1-4) : 35 - 38
  • [7] THERMAL-NEUTRON DOSIMETRY USING ELECTROCHEMICALLY ETCHED CR-39 DETECTOR
    ILIC, R
    KRISTOF, ES
    DIJANOSIC, R
    SKVARC, J
    DOBNIKAR, R
    RADIATION MEASUREMENTS, 1995, 25 (1-4) : 453 - 456
  • [8] Monitoring fast neutron flux inside spent reactor fuel by CR-39 detector
    Institute of Isotope and Surface Chemistry, PO Box 77, H-1525 Budapest, Hungary
    Radiat. Meas., 1600, 1-6 (601-603):
  • [9] Monitoring fast neutron flux inside spent reactor fuel by CR-39 detector
    Tam, NC
    Lakosi, L
    RADIATION MEASUREMENTS, 2001, 34 (1-6) : 601 - 603
  • [10] APPLICATION OF THE CR-39 DETECTOR FOR NEUTRON MEASUREMENTS IN A SPENT FUEL-STORAGE POND
    SUTEJ, T
    NAJZER, M
    NUCLEAR TRACKS AND RADIATION MEASUREMENTS, 1993, 21 (03): : 437 - 439