Refine your search:     
Report No.
 - 
Search Results: Records 1-20 displayed on this page of 33

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

Validation of the physical and RBE-weighted dose estimator based on PHITS coupled with a microdosimetric kinetic model for proton therapy

Takada, Kenta*; Sato, Tatsuhiko; Kumada, Hiroaki*; Koketsu, Junichi*; Takei, Hideyuki*; Sakurai, Hideyuki*; Sakae, Takeji*

Journal of Radiation Research, 59(1), p.91 - 99, 2018/01

 Times Cited Count:32 Percentile:87.69(Biology)

Evaluation of the relative biological effectiveness (RBE)-weighted dose is indispensable in the treatment planning of proton and carbon ion therapies. In this study, we validate the RBE-weighted dose calculated by microdosimetric kinetic model (MKM) in tandem with the Monte Carlo particle transport code PHITS for proton therapy using the full simulation geometry for the beam line of the Proton Medical Research Center at the University of Tsukuba. The physical dose and RBE-weighted dose on the central axis for a 155 MeV monoenergetic and spread-out Bragg peak beam of 60 mm width are evaluated by the method. The calculated results generally agree with the corresponding experimental data very well, though overestimations by approximately 3.2% and 15% at the maximum are observed for the physical and RBE-weighted doses, respectively. This research completes the computational microdosimetric approach based on a combination of PHITS and MKM for all types of radiotherapy that require RBE evaluations.

JAEA Reports

Investigation on cause of malfunction of Wide Range Monitor (WRM) in High Temperature engineering Test Reactor (HTTR); Sample tests and destructive tests

Shinohara, Masanori; Motegi, Toshihiro; Saito, Kenji; Haga, Hiroyuki; Sasaki, Shinji; Katsuyama, Kozo; Takada, Kiyoshi*; Higashimura, Keisuke*; Fujii, Junichi*; Ukai, Takayuki*; et al.

JAEA-Technology 2012-032, 29 Pages, 2012/11

JAEA-Technology-2012-032.pdf:6.57MB

An event, in which one of WRMs were disabled to detect the neutron flux in the reactor core, occurred during the period of reactor shut down of HTTR in March, 2010. The actual life time of WRM was unexpectedly shorter than the past developed life time. Investigation of the cause of the outage of WRM toward the recovery of the life time up to the past developed life is one of the issues to develop the technology basis of HTGR. Then, two experimental investigations were carried out to reveal the cause of the malfunction by specifying the damaged part causing the event in the WRM. One is an experiment using a mock-up sample test which strength degradation on assembly accuracy and heat cycle to specify the damaged part in the WRM. The other is a destructive test in FMF to specify the damaged part in the WRM. This report summarized the results of the destructive test and the experimental investigation using the mock-up to reveal the cause of malfunction of WRM.

Journal Articles

Stress corrosion cracking behavior of type 304 stainless steel irradiated under different neutron dose rates at JMTR

Kaji, Yoshiyuki; Kondo, Keietsu; Aoyagi, Yoshiteru; Kato, Yoshiaki; Taguchi, Taketoshi; Takada, Fumiki; Nakano, Junichi; Ugachi, Hirokazu; Tsukada, Takashi; Takakura, Kenichi*; et al.

Proceedings of 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (CD-ROM), p.1203 - 1216, 2011/08

In order to investigate the effect of neutron dose rate on tensile property and irradiation assisted stress corrosion cracking (IASCC) growth behavior, the crack growth rate (CGR) test, tensile test and microstructure observation have been conducted with type 304 stainless steel specimens. The specimens were irradiated in high temperature water simulating the temperature of boiling water reactor (BWR) up to about 1dpa with two different dose rates at the Japan Materials Testing Reactor (JMTR). The radiation hardening increased with the dose rate, but there was little effect on CGR. Increase of the yield strength of specimens irradiated with the low dose rate condition was caused by the increase of number density of frank loops. Little difference of radiation-induced segregation at grain boundaries was observed in specimens irradiated by different dose rates. Furthermore, there was little effect on local plastic deformation behavior near crack tip in the crystal plasticity simulation.

JAEA Reports

Differential pressure analysis for ventilation filter by smoke under fire accident with CELVA-1D

Watanabe, Koji; Tashiro, Shinsuke; Abe, Hitoshi; Takada, Junichi; Morita, Yasuji

JAERI-Tech 2004-029, 48 Pages, 2004/03

JAERI-Tech-2004-029.pdf:3.19MB

In a part of building ventilating installation of a nuclear fuel facility, a reprocessing plant for example, the pre-filters are adopted as one of the ventilation filters. In a fire accident, it is supposed that, because of the pre-filter clogging by large smoke, its differential pressure ($$Delta$$p) is evolved up to the value at its breakage. Therefore, in regard to maintaining the confinement of radioactive materials, it is important to predict the time course of $$Delta$$p of the pre-filter accurately. In the current study, it was assumed that the empirical equation for the DF of the pre-filter as function of smoke particle diameter (SPD), between 0.7-2 $$mu$$m, could be applied to estimating its DF for SPD above 2 $$mu$$m. Under this assumption, the time corresponding to its $$Delta$$p at its breakage, calculated by CELVA-1D, was agreed well with the experimental result.

JAEA Reports

Revaluation of JACS code system benchmark analyses of the heterogeneous system; Fuel rods in U+Pu nitric acid solution system

Takada, Tomoyuki; Miyoshi, Yoshinori; Katakura, Junichi

JAERI-Tech 2003-036, 80 Pages, 2003/03

JAERI-Tech-2003-036.pdf:3.67MB

In order to perform accuracy evaluation of the critical calculation by the combination of multi-group constant library MGCL and 3-dimensional Monte Carlo code KENO-IV among critical safety evaluation code system JACS, benchmark calculation was carried out from 1980 in 1982. Some cases where the neutron multiplication factor calculated in the heterogeneous system in it was less than 0.95 were seen. In this report, it re-calculated by considering the cause about the heterogeneous system of the U+Pu nitric acid solution systems containing the neutron poison shown in JAERI-M 9859. The present study has shown that the keff value less than 0.95 given in JAERI-M 9859 is caused by the fact that the water reflector below a cylindrical container was not taken into consideration in the KENO-IV calculation model. By taking into the water reflector, the KENO-IV calculation gives a keff value greater than 0.95 and a good agreement with the experiment.

JAEA Reports

Release behavior of smoke and clogging characteristics of the ventilation filter under the fire accident (Contract research)

Takada, Junichi; Hayashi, Shiro*; Watanabe, Koji; Takita, Koji*; Tsukamoto, Michio; Tashiro, Shinsuke; Abe, Hitoshi*; Uchiyama, Gunzo*

JAERI-Tech 2002-102, 87 Pages, 2003/01

JAERI-Tech-2002-102.pdf:3.27MB

no abstracts in English

Journal Articles

Development of a remote-controlled fatigue test machine using a laser extensometer in Hot Laboratory for study of irradiation effect on fatigue properties

Ishii, Toshimitsu; Yonekawa, Minoru; Omi, Masao; Takada, Fumiki; Saito, Junichi; Ioka, Ikuo; Miwa, Yukio

KAERI/GP-192/2002, p.157 - 166, 2002/00

no abstracts in English

JAEA Reports

Evaluation of released source terms from burning mock combustible waste

Abe, Hitoshi; Watanabe, Koji*; Tashiro, Shinsuke; Takada, Junichi; Uchiyama, Gunzo

JAERI-Research 2001-052, 18 Pages, 2001/11

JAERI-Research-2001-052.pdf:1.83MB

no abstracts in English

JAEA Reports

Safety demonstration tests on thermal decomposition of nitrated solvent with nitric acid in nuclear fuel reprocessing plants (Contract research)

Tsukamoto, Michio; Takada, Junichi; Koike, Tadao; Watanabe, Koji*; Miyata, Teijiro*; Nishio, Gunji*; Murata, Mikio*; Uchiyama, Gunzo

JAERI-Tech 2001-031, 47 Pages, 2001/03

JAERI-Tech-2001-031.pdf:2.75MB

no abstracts in English

JAEA Reports

Aerosol generation tests on thermal decomposition of organic solvent with nitric acid in nuclear fuel reprocessing plants (Contract research)

Tsukamoto, Michio; Takada, Junichi; Koike, Tadao; Watanabe, Koji*; Miyata, Teijiro*; Nishio, Gunji*; Murata, Mikio

JAERI-Tech 2000-036, p.43 - 0, 2000/03

JAERI-Tech-2000-036.pdf:2.27MB

no abstracts in English

JAEA Reports

Characteristics and mechanism of explosive reactions Purex solvent reactions with nitric acid at elevated temperatures (Contract research)

Miyata, Teijiro*; Takada, Junichi; Ida, Masaaki*; Nakagiri, Naotaka*; Koike, Tadao; Tsukamoto, Michio; Watanabe, Koji*; Nishio, Gunji*

JAERI-Tech 2000-035, p.64 - 0, 2000/03

JAERI-Tech-2000-035.pdf:3.17MB

no abstracts in English

JAEA Reports

Cause finding experiments and environmental analysis on the accident of the fire and explosion in TRP bituminization facility

Fujine, Sachio; Murata, Mikio; Abe, Hitoshi; Takada, Junichi; Tsukamoto, Michio; Miyata, Teijiro*; Ida, Masaaki*; Watanabe, Makio; Uchiyama, Gunzo; Asakura, Toshihide; et al.

JAERI-Research 99-056, p.278 - 0, 1999/09

JAERI-Research-99-056.pdf:22.73MB

no abstracts in English

Journal Articles

Generation of smoke and clogging of ventilation filter under burning of bitumen/salt mixture

Abe, Hitoshi; Takada, Junichi; Tsukamoto, Michio; *; Murata, Mikio

Journal of Nuclear Science and Technology, 36(7), p.619 - 625, 1999/07

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

no abstracts in English

JAEA Reports

Synthesis and identification of organic components of ``Red Oil'' (Contract research)

Miyata, Teijiro; Takada, Junichi; Nakagiri, Naotaka*; Koike, Tadao; Tsukamoto, Michio; *; Nishio, Gunji*

JAERI-Tech 99-040, 194 Pages, 1999/05

JAERI-Tech-99-040.pdf:5.73MB

no abstracts in English

JAEA Reports

Investigation of the exothermic characteristics of purex solvents and its main degradation products in the presence of nitric acid (Contract research)

Miyata, Teijiro; Takada, Junichi; Ida, Masaaki*; Nakagiri, Naotaka*; Tsukamoto, Michio; Koike, Tadao; *; Nishio, Gunji*

JAERI-Tech 99-039, 70 Pages, 1999/05

JAERI-Tech-99-039.pdf:2.78MB

no abstracts in English

Journal Articles

Behavior of radioactive aerosols in cell-ventillation system in reprocessing plants

Murata, Mikio; Takada, Junichi; Tsukamoto, Michio

KURRI-KR-30, p.5 - 11, 1998/00

no abstracts in English

Journal Articles

Aerosol removal by $$gamma$$-ray irradiation

*; Takada, Junichi

Earozoru Kenkyu, 12(1), p.50 - 56, 1997/00

no abstracts in English

JAEA Reports

Safety demonstration tests on pressure rise in ventilation system and blower integrity of a fuel-reprocessing plant

Takada, Junichi; Suzuki, Motoe; Tsukamoto, Michio; Koike, Tadao; *

JAERI-Tech 96-054, 237 Pages, 1996/12

JAERI-Tech-96-054.pdf:6.22MB

no abstracts in English

JAEA Reports

Removal of electric-charged aerosols by radiation effect

Nishio, Gunji; Takada, Junichi; *; Murata, Mikio; Abe, Hitoshi; *

JAERI-Research 95-064, 45 Pages, 1995/09

JAERI-Research-95-064.pdf:1.61MB

no abstracts in English

JAEA Reports

Thermochemical test of solvent in nuclear fuel reprocessing plants

Nishio, Gunji; Koike, Tadao; Miyata, Teijiro; Takada, Junichi; *

JAERI-Tech 95-029, 59 Pages, 1995/03

JAERI-Tech-95-029.pdf:1.76MB

no abstracts in English

33 (Records 1-20 displayed on this page)