JAEA-Review-2010-065.pdf:15.99MB - 日本原子力研究開発機構
JAEA-Review-2010-065.pdf:15.99MB - 日本原子力研究開発機構
JAEA-Review-2010-065.pdf:15.99MB - 日本原子力研究開発機構
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Systematic Measurement of Neutron and<br />
Gamma-ray Yields on Thick Targets Bombarded with<br />
18 MeV Protons<br />
M. Hagiwara a) , T. Sanami a) , Y. Iwamoto b) , N. Matsuda b) , Y. Sakamoto b) , Y. Nakane c) ,<br />
H. Nakashima c) , K. Masumoto a) , Y. Uwamino d) and H. Kaneko e)<br />
a) Radiation Science Center, KEK, b) Division of Environment and Radiation Sciences, NSED, <strong>JAEA</strong>,<br />
c) Safety Division, J-PARC, <strong>JAEA</strong>, d) Nishina Center for Accelerator-Based Science, RIKEN,<br />
e) Department of Advanced Radiation Technology, TARRI, <strong>JAEA</strong><br />
Nuclear data on proton-induced neutron and -ray<br />
production in the energy range from 10 to 20 MeV is<br />
important to execute the shield design and to estimate<br />
activation of low-energy accelerator facilities for medical use<br />
such as production of radiopharmaceuticals in positron<br />
emission tomography (PET) and a neutron source of an<br />
accelerator-based boron neutron capture therapy (BNCT).<br />
A number of cyclotrons are installed in medical facilities to<br />
produce positron emission radioisotopes such as 18 F through<br />
the 18 O(p,n) 18 F reaction for label tracers used in PET.<br />
The 9 Be(p, n) reaction is one of possible neutron sources used<br />
in an accelerator-based BNCT. These nuclear reactions<br />
simultaneously produce neutrons and -rays, and neutrons<br />
severely activate the accelerator components and the<br />
cyclotron room. The energy and angular distribution of<br />
neutrons should be estimated for radiation safety as well as<br />
clearance of the facility decommission.<br />
However, the experimental data on the energy and<br />
angular distribution for neutron and -ray production are<br />
very scarce especially for proton energies from 10 to<br />
20 MeV. Currently, shielding of the neutrons and -rays as<br />
well as activation of accelerator components and the room<br />
wall are calculated by using calculation codes such as<br />
PHITS 1) and MCNPX 2) . The accuracy of the codes for<br />
such a low energy region should be checked by experimental<br />
data, because most of physical models implemented in the<br />
codes were developed to describe reactions of high-energy<br />
particles. In this report, we describe the measurement of<br />
neutron and -ray energy spectra from various targets ( 9 Be,<br />
Neutron flux (n·MeV -1 ·sr -1 ·C -1 )<br />
4-33<br />
10 1<br />
10 2<br />
10 3<br />
10 4<br />
10 5<br />
10 6<br />
10 7<br />
10 8<br />
10 9<br />
10 10<br />
15 deg.x10 -1<br />
30 deg. x10 -2<br />
60 deg. x10 -3<br />
90 deg. x10 -4<br />
120 deg. x10 -5<br />
150 deg. x10 -6<br />
0 deg.<br />
Beryllium, p18 MeV<br />
Present<br />
ENDF/B-VII<br />
Bertini+Dresner<br />
10<br />
0 3 6 9 12 15 18<br />
0<br />
Energy (MeV)<br />
Fig. 1 Energy spectra of neutrons from thick beryllium<br />
target induced by 18 MeV proton bombardment.<br />
<strong>JAEA</strong>-<strong>Review</strong> <strong>2010</strong>-065<br />
- 157 -<br />
nat C, 27 Al, nat Cu and 181 Ta) induced by protons, and<br />
comparisons between the experimental data and calculation<br />
results.<br />
The experiments were carried out with 18 MeV proton<br />
beams delivered to the HB-1 beam line at the AVF cyclotron<br />
of TIARA. The targets are installed in a vacuum chamber.<br />
The NE213 organic liquid scintillators (5.08 cm in diameter<br />
and 5.08 cm in length) were placed in directions of 0, 15, 30,<br />
45, 60, 90, 120 and 150 o at a distance of 2.0 - 4.0 m from the<br />
target to measure the light outputs by neutrons and -rays,<br />
and the time-of-flight (TOF). The events of neutrons and<br />
-rays were separated by using a pulse shape discrimination<br />
technique and these energy spectra were analyzed by the<br />
TOF method and the unfolding method with FERDOU<br />
code 2) , respectively. Figure 1 and 2 show the typical<br />
neutron energy spectra with comparison between measured<br />
and calculation results using MCNPX with ENDF/B-VII<br />
data library and implemented physical models (Bertini +<br />
Dresner model) for beryllium, and using PHITS with LA150<br />
data library for aluminum. The calculation results generally<br />
well reproduce the measured energy spectra.<br />
We will continue systematic measurements of neutron<br />
and -ray spectra from accelerator components induced by<br />
lower energy proton bombardment to check the accuracy of<br />
evaluated data libraries and calculation codes.<br />
References<br />
1) H. Iwase et al., J. Nucl. Sci. Tech. 39 (2002) 1142.<br />
2) M. B. Chadwick et al., Nucl. Sci. Eng. 131 (1999) 293.<br />
3) K. Shin et al., Nucl. Tech. 53 (1981) 78.<br />
Neutron flux (n·MeV -1 ·sr -1 ·C -1 )<br />
10 2<br />
10 3<br />
10 4<br />
10 5<br />
10 6<br />
10 7<br />
10 8<br />
15 deg.x10 -1<br />
30 deg. x10 -2<br />
60 deg. x10 -3<br />
90 deg. x10 -4<br />
120 deg. x10 -5<br />
150 deg. x10 -6<br />
0deg.<br />
10 1<br />
Aluminum, p18 MeV<br />
Present<br />
LA150<br />
10<br />
0 3 6 9 12 15<br />
0<br />
Energy (MeV)<br />
Fig. 2 Energy spectra of neutrons from the aluminum<br />
target induced by 18 MeV proton bombardment.