title: Benchmarking of activation reaction distribution in an intermediate energy neutron field.
abstract: Neutron-induced reaction rate depth profiles inside concrete shield irradiated by intermediate energy neutron were calculated using a Monte-Carlo code and compared with an experiment. An irradiation field of intermediate neutron produced in the forward direction from a thick (stopping length) target bombarded by 400 MeV nucleon(-1) carbon ions was arranged at the heavy ion medical accelerator in Chiba. Ordinary concrete shield of 90 cm thickness was installed 50 cm downstream the iron target. Activation detectors of aluminum, gold and gold covered with cadmium were inserted at various depths. Irradiated samples were extracted after exposure and gamma-ray spectrometry was performed for each sample. Comparison of experimental and calculated shows good agreement for both low- and high-energy neutron-induced reaction except for (27)Al(n,X)(24)Na reaction at the surface.
authors.affiliation: Department of Nuclear Engineering and Management, School of Engineering, The University of Tokyo, 2-11-6 Yayoi, Bunkyo, Tokyo 113-8656, Japan. ogawa@n.t.u-tokyo.ac.jp
authors.forename: Tatsuhiko
authors.initials: T
authors.lastname: Ogawa
authors.forename: Mikhail N
authors.initials: MN
authors.lastname: Morev
authors.forename: Masahiro
authors.initials: M
authors.lastname: Hirota
authors.forename: Takuya
authors.initials: T
authors.lastname: Abe
authors.forename: Yuya
authors.initials: Y
authors.lastname: Koike
authors.forename: Satoshi
authors.initials: S
authors.lastname: Iwai
authors.forename: Takeshi
authors.initials: T
authors.lastname: Iimoto
authors.forename: Toshiso
authors.initials: T
authors.lastname: Kosako
mesh_terms: D003198:Computer Simulation; D020450:Heavy Ions; D018499:Linear Energy Transfer; D009010:Monte Carlo Method; D009502:Neutrons; D010315:Particle Accelerators; D011829:Radiation Dosage; D011835:Radiation Protection; D013051:Spectrometry, Gamma