A new area multidetector dosemeter for mixed n-gamma fields.
A new instrument to assess neutron ambient doses has been designed and constructed. In its design, spectrometric capabilities have been implemented that allow to take into account the energy spectrum of the neutron field in the evaluation of the operational magnitude, ambient dose equivalent, H*(10). This dosemeter is based on the moderation-absorption technique and can be employed over a wide range of energies from thermal to 20 MeV. It consists of a spherical shaped polyethylene moderator with a set of thermoluminescence dosemeters (TLDs) inserted in different positions of its interior to evaluate the external neutron energy spectrum. At this moment the system uses pairs 6LiF:Mg,Ti (TLD-600) and 7LiF:Mg,Ti (TLD-700) thermoluminescence dosemeters for a better gamma discrimination. The dosemeter response matrix was calculated using the MCNP4C Monte Carlo code (MC). The viability of the dosemeter for area dosemetry has been examined experimentally showing its capabilities over a wide range of energies.
Muñiz
J L
JL
Dosimetría de Radiaciones, CIEMAT, Madrid, Spain. joseluis.muniz@ciemat.es
Vicente
M C
MC
González
E M
EM
Romero
A M
AM
Embid
M
M
Delgado
A
A
D000465:Algorithms; D003198:Computer Simulation; D004781:Environmental Exposure / Q000032:analysis; D004867:Equipment Design; D019544:Equipment Failure Analysis / Q000379:methods; D018499:Linear Energy Transfer; D015233:Models, Statistical; D009010:Monte Carlo Method; D009502:Neutrons; D016273:Occupational Exposure / Q000032:analysis*; D011829:Radiation Dosage; D011835:Radiation Protection / Q000295:instrumentation* / Q000379:methods; D011868:Radioisotopes / Q000032:analysis*; D011874:Radiometry / Q000295:instrumentation* / Q000379:methods; D015203:Reproducibility of Results; D012542:Scattering, Radiation; D012680:Sensitivity and Specificity; D013051:Spectrometry, Gamma / Q000295:instrumentation* / Q000379:methods; D014159:Transducers
D011868:Radioisotopes