JAEA-Conf 2011-002 - 日本原子力研究開発機構

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4. Off line data analysis Double differential cross sections were determined through off-line analysis. The recorded pulse heights of signals were converted into particle energy using the Bethe-Bloch equation [4] and the Birks equation [1] taking into account the nonlinearity between light output and energy deposition. Particle identification was carried out by using PI technique [5]. The particle identification quantity, PI, is given by, b total PI E ( E E) , (2) total Where Etotal is the total energy deposited in the spectrometer, the E is the amount of energy deposited in the transmission detector and b is the parameter whose value was employed to be 1.73 to obtain best separation. 5. Conclusion In order to develop a new detector system, we have investigated the light output response and peak efficiencies of BGO crystals with respect to Proton and Alpha particles. The BGO crystal has good properties for the needs of our measurements. The experimental results showed a good agreement with the calculated curves by Birks equation. References: JAEA-Conf 2011-002 [1] J.B. Birks. “The Theory and Practice of Scintillation Counting” (Macmillan, New York) 1994. [2] EA Bakkum, Van Engelen, R.Kamermans et al., Nucl. Instr. & Meth. 225, 46 (1984). (330-334) [3] T. Kin et al., Physical Revew C, Vol.72, 014606 1-9 (2005). [4] N.Tsoulfanidis, Measurement and Detection of Radiation, Second Edition, Taylor & Francis, p. 124, 1995. [5] Makino, M., Eisburg, R., Inghum, D. and Waddell, C.: “A Method for Reducing the Effect of Nuclear Reaction in Stopping Detectors”, Nuclear Instruments and Methods, Vol. 81, pp. 125-131, 1970. b
Measurementof Neutron-Production Double-Differential Cross Sections for 290 MeV/u Oxygen Ion Incidence *Daisuke MORIGUCHI a , Haruhiko UEHARA a , Tsuyoshi KAJIMOTO a Keiichi HIRABAYASHI a , Hidetaka HIRANO a , Tomoya NISHIZAWA a Nobuhiro SHIGYO a , Yusuke UOZUMI a , Daiki SATOH b , Toshiya SANAMI c Yusuke KOBA d , Masashi TAKADA d , Naruhiro MATSUFUJI d aDepartment of Applied Quantum Physics and Nuclear Engineering Kyushu University 744 Motooka, Nishi-ku, Fukuoka 819-0395, Japan bJapan Atomic Energy Agency 2-4 Shirakatashirane, Tokai, Naka-gun, Ibaraki 319-1184, Japan cHigh Energy Accelerator Research Organization 1-1 O-ho, Tsukuba, Ibaraki 305-0801, Japan dNational Institute of Radiological Sciences 4-9-1 Anagawa, Inage-ku, Chiba 263-8555, Japan email : moriguchi@kune2a.nucl.kyushu-u.ac.jp Neutron-production double-differential cross sections for 290 MeV/u oxygen ion incidence on carbon target were measured with NE213 liquid organic scintillators by time-of-flight technique. NE213 liquid organic scintillators 12.7 cm in diameter and 12.7 cm thick were placed in the directions of 15 ◦ ,30 ◦ ,45 ◦ ,60 ◦ ,75 ◦ and 90 ◦ . The typical flight path length was 4.0 m. In order to reduce neutrons from the beam dump, an iron and a concrete shield was placed between the detectors and the beam dump. For measurement of background, a shadow bar was set between the target and each detector. Neutron detection efficiencies were obtained by calculations with a Monte Carlo simulation code SCINFUL-QMD. The cross sections were obtained for neutron energy above 3.6 MeV. The experimental results were compared with the calculation data of the PHITS2 code. 1. Intorduction JAEA-Conf 2011-002 As increasing the number of patients enrolled in carbon-ion cancer therapy, the potential risk of radiation-induced second cancers has become a serious issue, especially for young patients [1, 2]. It is thus important to investigate the risk, including the contribution of secondary particles that are inevitably produced within the patient and beam line devices due to the potency of their biological effect. In particular, it is important to know contribution of secondary neutrons because the secondary neutron has a strong penetrability and gives undesired dose to normal tissues in a wide area [3]. Recently, a plan to investigate contribution of secondary neutron using simulation codes is furthered. However, the reliability of calculation codes has been evaluated limitedly, because the
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JAEA-Conf 2011-002 Proceedings of t
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JAEA-Conf 2011-002 31. Preliminary
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6.2 Measurement of neutron-induced
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JAEA-Conf 2011-002 Table 1 Comparis
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JAEA-Conf 2011-002 (T1/2=8,900,000
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JAEA-Conf 2011-002 Though words too
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JENDL-3.3 showed better applicabili
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ENDF. Thus this cross section store
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Acknowledgement JAEA-Conf 2011-002
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In the MALIBU program, isotope conc
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some minor actinides. For major act
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JAEA-Conf 2011-002 code MVP-BURN an
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JAEA-Conf 2011-002 [3] Measurements
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3.1 Experimental Set up JAEA-Conf 2
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References JAEA-Conf 2011-002 [1] N
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JAEA-Conf 2011-002 was large. The a
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JAEA-Conf 2011-002 4. Results and D
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Acknowledgments Present study inclu
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Fig. 1 A conceptural picture of the
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4. Theoretical studies Theoretical
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JAEA-Conf 2011-002 Fig.9 Comparison
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Ion source JAEA-Conf 2011-002 LE
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JAEA-Conf 2011-002 3. Readiness
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JAEA-Conf 2011-002
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JAEA-Conf 2011-002 Figure 1. An exa
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JAEA-Conf 2011-002 Figure 6. Compar
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JAEA-Conf 2011-002 calculation of d
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JAEA-Conf 2011-002 equilibrium emis
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JAEA-Conf 2011-002 Cowley et al. [1
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4. Conclusions We have compared nuc
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of MeV region with highest cosmic-r
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JAEA-Conf 2011-002 events can be id
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JAEA-Conf 2011-002 models and its p
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JAEA-Conf 2011-002 xx
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JAEA-Conf 2011-002 1. The recent ac
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JAEA-Conf 2011-002 4. Conceptual de
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The Institute's staff of about 280
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3. Nuclear Theory Laboratory JAEA-C
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JAEA-Conf 2011-002 References [1] P
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JAEA-Conf 2011-002 reaction 6 Li +
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Using the approximated distribution
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Fig.9 Spectrum of gamma-ray followi
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JAEA-Conf 2011-002 in the same way
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JAEA-Conf 2011-002 [7]. For example
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JAEA-Conf 2011-002 For
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JAEA-Conf 2011-002 (5.0-9.0MeV), a
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components, the 0.56Wt% for hydroge
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Sensitivities of curium isotope con
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decreases of (n,g) reaction rates,
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5. Conclusion JAEA-Conf 2011-002 Wi
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2. Foundation of sensitivity analys
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JAEA-Conf 2011-002 where f g and f
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Fig.1 Sensitivity coefficient of th
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An outline of core configurations o
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0.010% 0.000% -0.010% -0.020% -0.03
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To clarify what nuclides and reacti
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Calculation was performed by the MV
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among these libraries, and the diff
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JAEA-Conf 2011-002 - 日本原子力研究開発機構

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