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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.

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