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Journal Articles

The 2009's professional engineer second examination "Nuclear & Radiation"; Elective subject question and a commentary

Nakano, Tomohito*; Mizutani, Akira*; Abe, Sadayoshi; Tomida, Kazuo*; Handa, Hiroyuki*

Genshiryoku eye, 56(1), p.63 - 76, 2010/01

no abstracts in English

Journal Articles

Reliability evaluation of SPEEDI's prediction by comparison with calculated results based on meteorological observation data

Rintsu, Yuko*; Serizawa, Shigeru*; Yamazaki, Tetsuo*; Umeyama, Nobuaki*; Moriuchi, Shigeru*; Handa, Hiroyuki*; Onishi, Ryoichi*; Takemura, Morio*; Chino, Masamichi; Nagai, Haruyasu; et al.

Proceedings of 16th Pacific Basin Nuclear Conference (PBNC-16) (CD-ROM), 6 Pages, 2008/10

no abstracts in English

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

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.

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

Estimation of activity and dose distributions around a proton linac induced by beam spill

Nakashima, Hiroshi; Sasamoto, Nobuo; Sakamoto, Yukio; Kusano, Joichi; Hasegawa, Kazuo; Handa, Hiroyuki*; Hayashi, Katsumi*; Yamada, Kobun*; Abe, Teruo*

Journal of Nuclear Science and Technology, 37(Suppl.1), p.870 - 874, 2000/03

no abstracts in English

Journal Articles

None

; *; *; *

Nihon Genshiryoku Gakkai-Shi, 38(9), p.58 - 63, 1996/00

None

Journal Articles

JASPER Experiments and Analyses of IHX Sodium Activation and Gap Streaming Mockups

; *; *; *

Proceedings of 1996 Radiation Protection and Shielding Division Topical Meeting, 0 Pages, 1996/00

None

JAEA Reports

Summary report on analysis of JASPER experiments

Shono, Akira; Tsunoda, Hirokazu; Takemura, Morio; Handa, Hiroyuki

PNC TN9410 95-171, 280 Pages, 1995/06

PNC-TN9410-95-171.pdf:12.63MB

All experiments planned in the JASPER (Japanese-American Shielding Program for Experimental Research) project have been conducted from '85 to '92. Results obtained from the post-experimental analyses are described in the annual reports ('86$$sim$$'94). This report is intended to review and summarize the enormous information of the annual reports. For the evaluation, the following topics were chosen. (1)Bulk Shielding attenuation characteristics and analysis accuracy (2)Design-dependent shielding characteristics and analysis accuracy (3)Evaluation of the shielding cross section libraries (4)Improvements in shielding analysis methods. Major conclusions are briefly as follows. (a)Both bulk shielding attenuation characteristics and streaming characteristics of configurations consisting of several materials including boron-carbide(B$$_{4}$$C), graphite, stainless steel, sodium and etc. were clarified and the analysis accuracy confirmed. (b)JSDJ2 (based on the JENDL-2) was demonstrated to be a better cross section library for shielding analysis by reviewing experimental analyses results. (c)The shielding analysis system for fast reactors using a 2-dimensional discrete ordinates code as the standard has been improved and verified. (d)Useful experiences have been gained in verifying both a Monte Carlo code and a 3-dimensional discrete ordinates code, as well as in optimizing various parameters including those for mesh spacing techniques. Another objective of this report is to specify key information which will be useful to review JASPER. For this purpose, information on experiment and analysis is presented in a table format by each experimental item. All technical reports related to JASPER are listed.

JAEA Reports

DOG-II:Input data generator program for DOT 3.5 code

Koizumi, Koichi; *; *; *; *; Takatsu, Hideyuki; Seki, Yasushi; Sato, Satoshi

JAERI-M 92-106, 62 Pages, 1992/08

JAERI-M-92-106.pdf:1.0MB

no abstracts in English

JAEA Reports

JASPER Experiment analyses (VI)

Chatani, Keiji; ; ; ; *; *; *

PNC TN9410 92-076, 348 Pages, 1992/03

PNC-TN9410-92-076.pdf:7.32MB

JASPER (Japanese American Shielding Program of Experimental Researches) is the cooperative research program between PNC and US-DOE using TSF (Tower Shielding Facility) in ORNL (Oak Ridge National Laboratory) as the experiment facility. This report summarizes the works in FY'1991 as follows; Planning the experiment configuration for JASPER Program, Analyses of the JASPER Program experiment, Analyses of the former TSF experiment, and Development of the methods for FBR shielding analyses. (1)Analyses of the JASPER Program Experiment In FY'1991 Axial shield Experiment data were mainly analyzed, and some of In-vessel Fuel Storage (IVS) Experiment data were also analyzed. The Fast Reactor Shielding Analysis System developed by PNC has been applied to the analyses for JASPER Program experiments. (Axial Shield Experiment Analysis) Axial Shield Experiment was conducted from August 1990 through December 1990 as part of a continuing series of eight experimennts planned for the JASPER Program. The experiment serves not only to provide data for the verification of analysis system in calculating the neutron streaming in each design, but also to provide a basis for determining the shielding effectiveness of stainless steel (SS) and boron carbide (B$$_{4}$$C). four types of experimental configuration were used. The conclusions of the analyses are as follows: (a)For the spectrum modifier which provides a spectrum of neutron representative of those incident on the axial shield for the FBR core, the two-dimensional calculation showed good agreement with the experimental data. It was confirmed that the two-dimensional calculation could estimate the experimental data with almost the same accuracy as in the analyses for the Radial shield Attenuation and the Fission Gas Plenum Experiments. (b)For the homogeneous mockups, the two-dimensional ealculation could give the good agreement with the experimental data. (c)For the central blockage type mockups, in which the coolant flows ...

JAEA Reports

Shielding analyses of JOYO MK-II(I)-C

Nakao, Noboru*; Amada, Tatsuo*; Horie, Junnosuke*; Takeuchi, Jun*; Handa, Hiroyuki*; Sebata, Masao*

PNC TJ202 84-06, 235 Pages, 1984/06

PNC-TJ202-84-06.pdf:5.71MB
PNC-TJ202-84-06TR.pdf:3.69MB

no abstracts in English

Journal Articles

None

; *; *; *

Proceedings of 1996 Radiation Protection and Shielding Division Topical Meeting, , 

None

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