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Sato, Satoshi; Maki, Koichi*
Fusion Engineering and Design, 65(4), p.501 - 524, 2003/07
Times Cited Count：8 Percentile：49.89(Nuclear Science & Technology)no abstracts in English
Sakamoto, Yukio
KEK Proceedings 2001-14, p.236 - 242, 2001/06
no abstracts in English
Sawamura, Sadashi*
JNC TJ8400 2000-053, 41 Pages, 2000/02
Dose evaluation for direct radiation and skyshine from nuclear fuel facilities is one of the environment evaluation items. This evaluation is carried out by using some shielding calculation codes. Because of extremely few benchmark data of skyshine, the calculation has to be performed very conservatively. Therefore, the benchmark data of skyshine and the well-investigated code for skyshine would be necessary to carry out the rational evaluation of nuclear facilities. The purpose of this study is to obtain the benchmark data of skyshine and to investigate the calculation code for skyshine. In this fiscal year, the followings are investigated; (1)To improve the detection sensitivity of pulsed neutron measurement, two neutron detectors and some electronic circuits are added to the system constructed last year. (2)To estimate the neutron dose at the distant point from the facility instead of the commercialized rem-counter, a 
He detector with paraffin moderator is equipped to the system. (3)Using the new detection system, the skyshine of neutrons from 45Mev LINAC facility was measured in the distance up to 300m. The results show that the time structure of pulsed neutrons almost disappears at the further points than 150m. (4)In the distance from 90m to 300m ordinal total counting method without gate pulse are applied to detect the neutrons. (5)The experimental results of space dependency up to 300m is fitted fairly well by the Gui's response function.
*; Ishida, Toshihisa; *
JAERI-Tech 98-030, 38 Pages, 1998/08
no abstracts in English
Takemura, Morio*
PNC TJ9055 97-001, 112 Pages, 1997/03
With use of a standard groupwise shielding design library JSSTDL produced from the latest evaluated nuclear data library JENDL-3.2, experimental analyses for the Axial Shield Experiment (homogeneous and central blockage type shield configurations with B
C or stainless steel shield material) were performed. The results were compared with those obtained by the same analysis method and input data using JSDJ2 library that had been applied consistently to the JASPER experiment analyses. In general, the results with JSSTDL analyses are higher than those by JSDJ2 as were found in analyses in last year for the Radial Shield Attenuation Experiment and the Special Materials Experiment. Consideration was made on the discrepancies between JSSTDL and JSDJ2 analysis results of the Axial Shield Experiment and also those of the sodium configulation in the Radial Shield Attenuation Experiment. The former was done by exchange of macro cross section of each region, and the latter forcused on sodium cross section was done with use of cross section sensitivity analysis method. Compilation of the input data necessary for future reanalyses of important configurations in JASPER experiments, that were selected in previous study in last year, were continued and new data were added into the computer disk holding previous ones.
Sawamura, Sadashi*
PNC TJ1600 97-001, 77 Pages, 1997/03
no abstracts in English
Shirai, Nobutoshi; Sudo, Toshiyuki
PNC TN8460 95-001, 92 Pages, 1995/09
no abstracts in English
PNC TN9410 95-152, 211 Pages, 1995/05
This report describes the results of the JASPER (Japanese-American Shielding Program for Experimental Research) post experiment analysis conducted in JFY 1994. Reviewed items were chosen by considering the past discussions. Series of the JASPER experimental analyses ('86
'94) have been terminated and the review report is being published. Major conclusions of this report are briefly as follows. (Axial Shield Experiment) Monte Carlo code "MORSE" was employed in the analysis of Homogeneous, Rod-bundle and Central blockage configuration, respectively. C/E values of streaming factor are relatively good(0.950.98) for Bonner ball response, while around 20% underestimation is found in Hornyak button response. Good agreement is not always found between MORSE and two-dimensional discrete ordinates code DOT-3.5. (IN-Vessel Fuel Storage Experiment) U.S.-proposed configurations have been reviewed to finish all experimental analyses. These configurations have 1.8m-thick Na layer prior to the IVS mockup, which may soften neutron spectrum. They show almost same C/E values (0.801.01) as the Japan-proposed ones. Analysis accuracy on the IVS mockup is found to be -10+20%. (Intermediate Heat Exchanger Experiment) Three-dimensional discrete ordinates code "TORT" was employed in the analysis of a configuration which shows a complicated neutron flux distribution due to the BC Shield Prior to the sodium region. Various parameters including those for mesh spacing techniques were optimized. There exists around 15% discrepancy between TORT and MORSE, however, it is attributed to the different ways in obtaining input neutron flux.(Gap Streaming Experiment) Basic calculations were conducted in order to investigate a standard for selecting appropriate Sn quardratures sets. In analyzing configuration where neutron streaming is evident, biased setting toward a streaming direction would be useful to evaluate more exact flux distribution. ...
Chatani, Keiji; ; ; ; *; *; *
PNC TN9410 92-076, 348 Pages, 1992/03
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 (BC). 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 ...
Higashi, Kunio*; Shin, Kazuo*
PNC TJ2604 87-001, 31 Pages, 1987/03
no abstracts in English
Sekiguchi, Akira*;
JAERI-M 86-060, 267 Pages, 1986/04
no abstracts in English
; ; *
JAERI-M 7445, 26 Pages, 1977/12
no abstracts in English
; ; *; *; ; ; ; ; ; ; et al.
JAERI-M 5794, 71 Pages, 1974/07
no abstracts in English
Hashimoto, Shintaro; Sato, Tatsuhiko
no journal, ,
PHITS can simulate a behavior of various particles such as neutrons and photons, and has been used for shielding calculations in accelerator facilities. Reliability of PHITS based on the Monte Carlo method can be usually evaluated by statistical uncertainties related with the number of trials. However, uncertainty of input parameters such as densities and compositions of shielding materials might influence on results of the shielding calculation. Estimation of the influence as systematic uncertainties gives quantitative discussion of the calculation. We proposed a new method to estimate systematic uncertainties with ANOVA, and then applied the method to analysis of neutron shielding calculations. In the analysis, the effect of the uncertainty of water contents in concrete materials on neutron fluences could be estimated quantitatively.
Hashimoto, Shintaro
no journal, ,
PHITS can simulate a behavior of various radiation particles such as neutrons. The number of users is more than 4,000 in the world. For further spread of PHITS, we have validated the reliability and developed useful functions. Recently, we performed a benchmark study by comparing experimental data for various cases, and confirmed the reliability quantitatively. We implemented dose conversion factors, which were shown in ICRP Publication 116 and 123, into PHITS. By using this function, PHITS users can evaluate easily various effective doses and dose equivalents for shielding design of accelerator facilities or study of radiation protection. We are developing analysis functions; estimation of systematic uncertainties related to errors of input information, dependence on input information such as source energies, and convergence as the number of trials increases. We will introduce the current status of PHITS and the analysis functions implemented later.
