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JAEA Reports

Revised version of SSCAT; Simplified shielding calculation system for high energy proton accelerator facilities

Oguri, Tomomi*; Masukawa, Fumihiro; Nakane, Yoshihiro; Nakashima, Hiroshi

JAEA-Data/Code 2011-026, 25 Pages, 2012/03

JAEA-Data-Code-2011-026.pdf:2.07MB

The simplified shielding calculation (SSCAT) system is a calculation system for radiation shielding design of high energy proton accelerator facilities, based on Moyer's and Tesch's formulae for bulk shielding and Stapleton's formula for neutron skyshine. SSCAT was originally developed for conceptual shielding design calculations of the J-PARC (Japan Proton Accelerator Research Complex) facilities, and was recently revised in order to cope with safety analysis for the licensing of the J-PARC facilities and shielding design for other proton accelerator facility. This report describes the recent status of SSCAT.

Journal Articles

Estimation of radioactivity produced in cooling water at high-intensity proton accelerator facility

Masukawa, Fumihiro; Nakane, Yoshihiro; Iwamoto, Yosuke; Nakashima, Hiroshi

Nuclear Technology, 168(3), p.680 - 684, 2009/12

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

The radioactivity produced in the accelerator cooling water was estimated to draw up the maintenance scenario of the J-PARC accelerators. Activation cross section sets from Nitrogen and Oxygen were evaluated from the available experimental data and theoretically calculated data by INC/GEM and LAHET for high-energy proton and neutron. The PHITS and MCNPX codes were used to calculate the proton and neutron fluxes in the water-cooled accelerator components. The radioactivity from the corrosion product was also estimated by scaling of the measurements at KEK-PS and LAMPF. Tritium are estimated 5.7$$times$$10$$^{7}$$ [Bq] in LINAC and 2.5$$times$$10$$^{9}$$ [Bq] in 3-GeV Synchrotron by annual operation. Dose in machinery rooms by short-lived nuclides are reasonably low at LINAC, whereas $$sim$$10$$^{3}$$ times higher at 3-GeV Synchrotron. The estimation of tritium is acceptable level for the disposal to the environment, while short-lived nuclides at 3-GeV Synchrotron may make the facility maintenance difficult.

Journal Articles

Experimental studies of shielding and irradiation effects at high energy accelerator facilities

Nakashima, Hiroshi; Sakamoto, Yukio; Iwamoto, Yosuke; Matsuda, Norihiro; Kasugai, Yoshimi; Nakane, Yoshihiro; Masukawa, Fumihiro; Mokhov, N.*; Leveling, A.*; Boehnlein, D.*; et al.

Nuclear Technology, 168(2), p.482 - 486, 2009/11

BB2007-3640.pdf:0.22MB

 Times Cited Count:7 Percentile:47.42(Nuclear Science & Technology)

Experimental studies of shielding and radiation effects have been started using 120-GeV proton synchrotron at Fermi National Accelerator Laboratory (FNAL) under collaboration between FNAL and Japan. The first campaign of the experiment was carried out at the Pbar target station and Numi experimental station at FNAL, using antiproton and neutrino production targets irradiated by 120-GeV protons. The generated secondary particles passing through steel, concrete and rock were measured by activation methods as well as by other detectors such as scintillator with a veto counter, phoswich detector and a Bonner ball counter on trial. Preliminary experimental results are presented.

JAEA Reports

Development of SHINE3, simple code for high-energy neutron skyshine dose evaluation

Masukawa, Fumihiro; Abe, Teruo*; Hayashi, Katsumi*; Handa, Hiroyuki*; Nakashima, Hiroshi

JAEA-Data/Code 2006-024, 98 Pages, 2006/11

JAEA-Data-Code-2006-024.pdf:7.9MB

We have developed SHINE3, simple code for high energy neutron skyshine dose evaluation, for the shielding designs of high energy accelerator facilities. This code uses the 4-parametric fitting function to the skyshine dose response by neutron and secondary $$gamma$$-ray, which were predicted by PHITS, the general-purpose Particle and Heavy Ion Transport Monte Carlo code system. This code can be applied for skyshine dose evaluation of neutron up to 3 GeV in energy, and distance ranging between 10 and 2000 meters from source point, with equivalent accuracy as those by Monte Carlo Method.

Journal Articles

Development of crosslinked rubber material for high radiation field

Nakatsukasa, Sadayoshi*; Tabasaki, Takeshi*; Kusano, Joichi; Masukawa, Fumihiro

Nihon Gomu Kyokai-Shi, 79(9), p.429 - 434, 2006/09

A new compound was developed to obtain a radiation proof crosslinked rubber which shows the excellent performance than the usual elastomer i.e. ordinary EPDM(Ethylene-propylene-diene terpolymer) based one. As the first study,examinations were carried out with Co-60 $$gamma$$-ray exposure tests at the room temperature for various candidate rubbers. Based on the exposure test of various rubbers, EPDM compounds were investigated in order to improve the resistance to deterioration under high radiation field. The high performance rubber was achieved by a blend of EPDM and IIR(Butyl rubber). In addition to the polymer system, antioxidant and aromatic oil were used as admixture. The most excellent new crosslinked rubber showed no bleeding, no brooming, less change of hardness and keep 150% elongation after the $$gamma$$-ray irradiation over 7 MGy.

Journal Articles

Radiation shielding study for the J-PARC project

Nakashima, Hiroshi; Shibata, Tokushi; Nakane, Yoshihiro; Masukawa, Fumihiro; Matsuda, Norihiro; Iwamoto, Yosuke; Hirayama, Hideo*; Suzuki, Takenori*; Miura, Taichi*; Numajiri, Masaharu*; et al.

Proceedings of 14th Biennial Topical Meeting of the ANS Radiation Protection and Shielding Division (CD-ROM), p.267 - 282, 2006/00

no abstracts in English

Journal Articles

Radiation safety design for the J-PARC project

Nakashima, Hiroshi; Nakane, Yoshihiro; Masukawa, Fumihiro; Matsuda, Norihiro; Oguri, Tomomi*; Nakano, Hideo*; Sasamoto, Nobuo*; Shibata, Tokushi*; Suzuki, Takenori*; Miura, Taichi*; et al.

Radiation Protection Dosimetry, 115(1-4), p.564 - 568, 2005/12

 Times Cited Count:8 Percentile:50.68(Environmental Sciences)

The High Intensity Proton Accelerator Project, named as J-PARC, is in progress, aiming at studies on the latest basic science and the advancing nuclear technology. In the project, the high-energy proton accelerator complex of the world highest intensity is under construction. In order to establish a reasonable shielding design, both simplified and detailed design methods were used in the shielding design of J-PARC. This paper reviews the present status of the radiation safety design study for J-PARC.

Journal Articles

$$gamma$$-ray irradiation experiments of collimator key components for the 3GeV-RCS of J-PARC

Kinsho, Michikazu; Ogiwara, Norio; Masukawa, Fumihiro; Takeda, Osamu; Yamamoto, Kazami; Kusano, Joichi

Proceedings of 2005 Particle Accelerator Conference (PAC '05) (CD-ROM), p.1309 - 1311, 2005/00

It was success to develop the radiation resistant components using for beam collimator. Turbo molecular pump could be operated more than 15 MGy of $$gamma$$ ray irradiation dose. Stepping motor developed at JAERI could be operated with good performance in the $$gamma$$ ray dose of more than 70 MGy. PEEK sheathed cables and connector have kept good performance during $$gamma$$ ray irradiation more than the dose of 10 MGy. It was cleared that the function of the heat pipe disappeared at 30 kGy $$gamma$$ ray irradiation dose.

Journal Articles

Benchmark analyses of neutron streaming experiments for proton accelerator facilities

Nakano, Hideo*; Masukawa, Fumihiro; Nakashima, Hiroshi; Sasamoto, Nobuo*; Tayama, Ryuichi*; Handa, Hiroyuki*; Hayashi, Katsumi*

Journal of Nuclear Science and Technology, 41(Suppl.4), p.50 - 53, 2004/03

In order to estimate accuracy of the various calculation methods for the neutron streaming through a maze and duct in proton accelerator facilities, we performed benchmark analyses by using the radiation shielding design codes. According to the results of the benchmark analyses, it is concluded that NMTC/MCNP, MCNPX and DUCT-III are applicable to actual calculation of the duct-streaming radiations for J-PARC.

Journal Articles

Analyses of streamed neutron spectra at TIARA using DUCT-III

Masukawa, Fumihiro; Nakano, Hideo*; Nakashima, Hiroshi; Sasamoto, Nobuo; Tayama, Ryuichi*; Hayashi, Katsumi*; Shin, Kazuo*

Journal of Nuclear Science and Technology, 41(Suppl.4), p.46 - 49, 2004/03

A simple design code for duct-streaming radiations, DUCT-III was applied to the analyses of the streamed neutron spectra measured at TIARA labyrinth with two bends. The code satisfactorily reproduced the measured neutron energy spectra and the Monte Carlo calculations, except that every calculation overestimated the measured thermal components by factor of 2 or 3.

JAEA Reports

Verification of the DUCT-III for calculation of high energy neutron streaming

Masukawa, Fumihiro; Nakano, Hideo*; Nakashima, Hiroshi; Sasamoto, Nobuo; Tayama, Ryuichi*; Handa, Hiroyuki*; Hayashi, Katsumi*; Hirayama, Hideo*; Shin, Kazuo*

JAERI-Tech 2003-018, 42 Pages, 2003/03

JAERI-Tech-2003-018.pdf:1.7MB

no abstracts in English

Journal Articles

Evaluation of radioactivity at accelerator tunnels for high-intensity proton accelerator facility

Nakane, Yoshihiro; Masukawa, Fumihiro; Oguri, Tomomi*; Nakashima, Hiroshi; Abe, Teruo*; Sasamoto, Nobuo

Journal of Nuclear Science and Technology, 39(Suppl.2), p.1260 - 1263, 2002/08

no abstracts in English

Journal Articles

Analyses of high energy neutron streaming experiments using DUCT-III

Masukawa, Fumihiro; Nakashima, Hiroshi; Sasamoto, Nobuo; Nakano, Hideo*; Tayama, Ryuichi*

Journal of Nuclear Science and Technology, 39(Suppl.2), p.1268 - 1271, 2002/08

no abstracts in English

JAEA Reports

Burnup calculation code system COMRAD96

Suyama, Kenya; Masukawa, Fumihiro*; *; *; *; *

JAERI-Data/Code 97-021, 86 Pages, 1997/06

JAERI-Data-Code-97-021.pdf:2.3MB

no abstracts in English

JAEA Reports

Burnup code for fuel assembly by Monte Carlo code; MKENO-BURN

Naito, Yoshitaka; Suyama, Kenya; Masukawa, Fumihiro; Matsumoto, Kiyoshi; Kurosawa, Masayoshi; *

JAERI-Data/Code 96-037, 70 Pages, 1996/12

JAERI-Data-Code-96-037.pdf:1.68MB

no abstracts in English

Journal Articles

Monte Carlo analyses of benchmark experiments and accuracy to demonstrate shielding safety of nuclear fuel cycle facilities

Masukawa, Fumihiro; Sakamoto, Yukio; *

Proc., 1996 Topical Meeting on Radiation Protection and Shielding, 1, p.432 - 439, 1996/00

no abstracts in English

Journal Articles

Monte Carlo simulation of radiation shielding by parallelized MCNP4

; ; Masukawa, Fumihiro

Proc. of the 3rd Parallel Computing Workshop; PCW 94, 0, p.P2.G.1 - P2.G.9, 1994/00

no abstracts in English

Journal Articles

Parallelization of Monte Carlo code MCACE for shielding analysis and measurement of parallel efficiency on AP-1000 with 64 cell processors

; Masukawa, Fumihiro; Naito, Yoshitaka; *; *

Proc. of the Seminar on SCALE-4 and Related Modular Systems, 0, p.186 - 193, 1994/00

no abstracts in English

JAEA Reports

Parallelization of MCNP4 code by using simple FORTRAN algorithms

P.I.Yazid*; ; Masukawa, Fumihiro; Naito, Yoshitaka

JAERI-M 93-230, 78 Pages, 1993/12

JAERI-M-93-230.pdf:2.31MB

no abstracts in English

JAEA Reports

Parallelization of MCNP 4, a Monte Carlo neutron and photon transport code system, in highly parallel distributed memory type computer

Masukawa, Fumihiro; ; Naito, Yoshitaka; *; *; *; *

JAERI-M 93-210, 40 Pages, 1993/11

JAERI-M-93-210.pdf:1.24MB

no abstracts in English

46 (Records 1-20 displayed on this page)