Monte Carlo calculation and measurement of energy response of a solid state nuclear track detector to neutrons from 100 keV to 20 MeV

Nakane, Yoshibumi; Nakashima, Hiroshi; Sakamoto, Yukio

doi:10.1016/s1350-4487(97)00004-8

Cited by 9 publications

(2 citation statements)

References 13 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…The neutron sensitivities for the 5 and 15 MeV neutrons were lower than in previous measurements 24) because we measured only crossed tracks [types (a), (b), and (e) shown in Fig. 1] and rejected stopped tracks [type (c) shown in Fig.…”

Section: Neutron Sensitivitymentioning

confidence: 61%

Dosimetry for Neutrons from 0.25 to 15 MeV by the Measurement of Linear Energy Transfer Distributions for Secondary Charged Particles in CR-39 Plastic

Tawara¹,

Eda²,

Sanami³

et al. 2008

jjap

View full text Add to dashboard Cite

In the radiation fields of high energy accelerator facilities, high-altitude aircraft and space flights, high-energy neutron dosimetry of $20 MeV or more is a significant issue for radiological protection. We studied the feasibility of experimental measurements of linear energy transfer (LET) distributions for secondary charged particles induced by fast neutrons using CR-39 plastic nuclear track detectors. In order to investigate a method of analyzing the CR-39 detectors that is appropriate for fast neutron dosimetry, two-layer CR-39 stacks were exposed to monochromatic neutrons (0.25, 0.55, 5, and 15 MeV) at the Fast Neutron Laboratory of Tohoku University in Japan. We also conducted Monte Carlo calculations to estimate the detection efficiency of the CR-39 detector for recoil protons. The CR-39 detectors treated by single-step chemical etching were used to obtain LET distributions for LET > 10 keV/mm-water. The results indicated that measurements of short-range particles are very important for obtaining the correct LET distributions. Using the measured LET distributions, we calculated neutron sensitivities, absorbed doses and dose equivalents based on the ICRP 60 Q-L relation and averaged quality factors. The dose equivalents were compared with the neutron fluence-to-dose equivalent conversion factors given by ICRP 74 and the averaged quality factors were compared with weighting factors given by ICRP 60 and ICRP 92.

show abstract

Section: Neutron Sensitivitymentioning

confidence: 61%

Dosimetry for Neutrons from 0.25 to 15 MeV by the Measurement of Linear Energy Transfer Distributions for Secondary Charged Particles in CR-39 Plastic

Tawara¹,

Eda²,

Sanami³

et al. 2008

jjap

View full text Add to dashboard Cite

show abstract

“…The distinction between our calculations and similar ones carried out with the help of MCNP code usage (Lengar et al, 2003;Jamil et al, 1997) and with originally designed codes (Nakane et al, 1997;Meyer et al, 1998;Hermsdorf et al, 1999;Khan et al, 2001) is that we do not consider only protons, but also the alpha particles and other heavier ions which are generated, giving a total contribution which exceeds that of the protons alone for neutrons with energies more than 10 MeV.…”

Section: General Description Of Monte Carlo Simulationsmentioning

confidence: 99%