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Tada, Kenichi; Kondo, Ryoichi; Endo, Tomohiro*; Yamamoto, Akio*
Journal of Nuclear Science and Technology, 60(6), p.624 - 631, 2023/06
Times Cited Count：2 Percentile：50.96(Nuclear Science & Technology)The sensitivity analysis and the uncertainty quantification have an important role in improving the evaluated nuclear data library. The current computational performance enables us to the sensitivity analysis and uncertainty quantification using the continuous energy Monte Carlo calculation code. The ACE file perturbation tool was developed for these calculations using modules of FRENDY. This tool perturbs the microscopic cross section, the number of neutrons per fission, and the fission spectrum. The uncertainty quantification using the random sampling method is also available if the user prepares the covariance matrix. The uncertainty of the k-effective using the perturbation tool was compared to the current sensitivity analysis codes SCALE/TSUNAMI and MCNP/KSEN. The comparison results indicated that the random sampling method using this tool accurately estimates the uncertainty of k-effective.
Takai, Shizuka; Shimada, Taro; Takeda, Seiji; Koike, Katsuaki*
Journal of Contaminant Hydrology, 251, p.104097_1 - 104097_12, 2022/12
Times Cited Count：3 Percentile：46.08(Environmental Sciences)When assessing the risk from an underground environment that is contaminated by radioactive nuclides and hazardous chemicals and planning for remediation, the contaminant plume distribution and the associated uncertainty from measured data should be estimated accurately. While the release history of the contaminant plume may be unknown, the extent of the plume caused by a known source and the associated uncertainty can be calculated inversely from the concentration data using a geostatistical method that accounts for the temporal correlation of its release history and groundwater flow modeling. However, the preceding geostatistical approaches have three drawbacks: (1) no applications of the three-dimensional plume estimation in real situations, (2) no constraints for the estimation of the plume distribution, which can yield negative concentration and large uncertainties, and (3) few applications to actual cases with multiple contaminants. To address these problems, the non-negativity constraint using Gibbs sampling was incorporated into the geostatistical method with groundwater flow modeling for contaminant plume estimation. This method was then tested on groundwater contamination in the Gloucester landfill in Ontario, Canada. The method was applied to three water soluble organic contaminants: 1,4-dioxane, tetrahydrofuran, and diethyl ether. The effectiveness of the proposed method was verified by the general agreement of the calculated plume distributions of the three contaminants with concentration data from 66 points in 1982 (linear correlation coefficient of about 0.7). In particular, the reproduced large spill of organic contaminants of 1,4-dioxane in 1978 was more accurate than the result of preceding minimum relative entropy-based studies. The same peak also appeared in the tetrahydrofuran and diethyl ether distributions approximately within the range of the retardation factor derived from the fraction of organic carbon.
Takai, Shizuka; Shimada, Taro; Takeda, Seiji; Koike, Katsuaki*
Joho Chishitsu, 32(3), P. 95, 2021/09
We received best presentation award GEOINROUM-2021 for the presentation on "Estimation of contaminated materials concentration by a geostatistical method with groundwater flow". We submit the comments of impression for getting the Award to Geoinformatics.
Yamaki, Kenichi*; Kita, Satoshi*; Obayashi, Hironari; Ariyoshi, Gen; Saito, Shigeru; Sasa, Toshinobu
JAEA-Technology 2020-021, 26 Pages, 2021/02
JAEA-Technology-2020-021.pdf:2.34MB
As digitalization of measuring instruments, Programmable Logic Controller is mainly used for controlling large-scale devices, and many test devices are controlled in digital. Together with increase of the data storage capacity, it has become possible to record the measured values over the entire experimental period. By collecting the entire experimental data, it became easy to appropriately record the test environment during the corrosion test of materials and to analyze the changes and transients during continuous operation from various viewpoints. On the other hand, in a long-term test, the large number of measurement data were recorded, which requires long time for data processing and data extraction for analyses. In addition, it is necessary to pay attention to organize the data collected by different data formats. To solve these problems, a processing tool were produced to extract and process the data efficiently from the sequencer installed in the lead-bismuth test device.
Fujii, Shun*; Kato, Tetsu*; Kawamura, Yamato*; Tahara, Junichiro*; Baba, Shoichiro*; Sanada, Yukihisa
Proceedings of 26th International Symposium on Artificial Life and Robotics (AROB 26th 2021), p.280 - 285, 2021/01
In recent years, autonomously navigating unmanned vessels have been actively studied, and many of these vessels are designed to perform unmanned operations such as observation and transportation. On the other hand, this study uses an unmanned ship with a moon pool that collects seabed mud, which is difficult for ordinary ships. Vessels used since the area are highly turbulent due to wind, so it is necessary to maintain a fixed point and orientation when removing mud. The ship is equipped with side thrusters to maintain a fixed point and bow direction. In this study, the control method was devised to maintain fixed point and orientation, and the control method is based on robust sliding mode control. The proposed control method was verified by simulation, and the desired behavior was confirmed.
Tamakuma, Yuki*; Yamada, Ryohei; Iwaoka, Kazuki*; Hosoda, Masahiro*; Kuroki, Tomohiro*; Mizuno, Hiroyuki*; Yamada, Koji*; Furukawa, Masahide*; Tokonami, Shinji*
Perspectives in Science (Internet), 12, p.100414_1 - 100414_4, 2019/09
In this study, a portable radioactive plume monitor using a silicon photodiode was developed for the detection of a radioactive plume (e.g. 
I, 
Cs and 
Cs) in an emergency situation. It was found that the background count rate was proportional to ambient dose equivalent rate and the detection limit for the monitor at 20 
Sv h
as an ambient dose equivalent rate was evaluated to be 187 Bq m
using the ISO11929 method. These results suggest that the detection limit for the system can be decreased effectively by lead shielding with optimized thickness.
Kondo, Ryoichi*; Endo, Tomohiro*; Yamamoto, Akio*; Tada, Kenichi
Proceedings of International Conference on Mathematics and Computational Methods applied to Nuclear Science and Engineering (M&C 2019) (CD-ROM), p.1493 - 1502, 2019/00
A perturbation capability of ACE formatted cross section files was developed using the modules of FRENDY. Uncertainty quantification using MCNP was carried out for the Godiva critical experiment by the RS method. We verified the results of the RS method by comparing with those obtained by the conventional sensitivity analyses. Moreover, uncertainty reduction using the bias factor method with the RS technique was applied to kinetic parameter, i.e., neutron generation time.
Stankovskiy, A.*; Iwamoto, Hiroki; 
elik, Y.*; Van den Eynde, G.*
Annals of Nuclear Energy, 120, p.207 - 218, 2018/10
Times Cited Count：8 Percentile：62.29(Nuclear Science & Technology)Propagation of high-energy (above 20-MeV) nuclear data uncertainties on the safety related neutronic responses in accelerator driven systems has been assessed. The total core power and production of radionuclides contributing to radiation source terms were focused on. The article features a method based on the Monte Carlo sampling of random nuclear data files from the covariance matrices generated from the sets of reaction cross sections obtained with model calculations of high-energy particle interactions with matter or picked up from already existing nuclear data libraries. It has been demonstrated that nuclear data uncertainties do not need to be propagated through particle transport calculations to obtain uncertainties on the responses. This advantage allowed to investigate the convergence of the sample average to the best estimate. The number of random nuclear data file sets needed to obtain reliable uncertainty on the total core power is around 300 that results in the uncertainty of 14%. The uncertainties on the concentrations of nuclides most important for the safety assessment that are accumulated in lead-bismuth eutectic during irradiation, range from 5 to 60%. Concentrations of some nuclides exemplified by Tritium converge much slower than neutron multiplicities so that several thousands of samples are needed to ensure reliable uncertainty estimates.
Yamamoto, Masahiko; Mori, Eito; Surugaya, Naoki
JAEA-Technology 2015-024, 19 Pages, 2015/09
JAEA-Technology-2015-024.pdf:19.11MB
Environmental Sampling from the hot cell in the Operating Testing Laboratory (OTL) of the Tokai Reprocessing Plant is implemented as an inspection of International Atomic Energy Agency (IAEA) for the first time. The specified sampling place requested from IAEA inspector is a device inside the hot cell. Since it is expected to be highly radioactive, the dose rates of samples and inside the hot cell are evaluated in advance. Also, the threshold dose rates of samples are determined. Subsequently, the sampling procedure describing radiation protection has been prepared. The environmental sampling from OTL hot cell is safely performed in accordance with the procedure and the radioactivity of sample is measured. The samples are categorized as Excepted Package according to the transport regulation and are transported to Safeguards Analytical Services of IAEA.
Magara, Masaaki
Kaku Busshitsu Kanri Senta Nyusu, 34(11), P. 18, 2005/11
no abstracts in English
Suzuki, Yoshio*; Takeshima, Yuriko; Ono, Nobuaki*; Koyamada, Koji*
Nihon Bacharu Riaritei Gakkai Rombunshi, 10(2), p.231 - 240, 2005/06
A volume rendering is widely used for intuitively understanding 3-dimensionaly distribution of physical quantities. When the quantities have a nest-like distribution, however, the inside distribution cannot be observed. As one of the solution, an immersive virtual reality (VR) system is useful, since the researcher can immersively observe the distribution by using such a system. However, a plane slice sampling method conventionally used in the volume rendering has a problem that the quality of visualized images deteriorates especially in the immersive VR system. To resolve the problem, a spherical surface sampling method is applied to the volume rendering in the immersive VR system. The quality of image and the display speed are compared between these two methods.
due to perturbed fission-source distributionNagaya, Yasunobu; Mori, Takamasa; Brown, F. B.*
Monte Karuro Keisanho Kodoka No Genjo; Dai-3-Kai Monte Karuro Shimyureshon Kenkyukai Hobunshu, p.105 - 115, 2004/12
The Monte Carlo perturbation method based on the differential operator sampling method has been widely used to obtain a small change in neutronic parameters or sensitivity. The method is very effective for fixed-source problems but a difficulty arises for eigenvalue problems because the fission source distribution is perturbed. Most Monte Carlo codes assume that the source distribution is unchanged after a perturbation is introduced. However, this assumption can lead to a significant error in the perturbation estimate. Recently, a method to estimate the perturbed fission source effect has been proposed. In this method, the additional weights for the differential coefficient of the fission source at fission sites are normalized in each cycle, and the effect is estimated by propagating the normalized additional weight between cycles. The method and benchmark results have been reviewed. It has been found that this method is very effective in perturbation calculations for the effective multiplication factor.
Esaka, Fumitaka; Sakurai, Satoshi
Kaku Busshitsu Kanri Senta Nyusu, 33(11), p.9 - 12, 2004/11
no abstracts in English
Ando, Masami; Tanigawa, Hiroyasu; Jitsukawa, Shiro; Sawai, Tomotsugu; Kato, Yudai*; Koyama, Akira*; Nakamura, Kazuyuki; Takeuchi, Hiroshi
Journal of Nuclear Materials, 307-311(Part1), p.260 - 265, 2002/12
Times Cited Count：39 Percentile：90.08(Materials Science, Multidisciplinary)no abstracts in English
Adachi, Takeo
Kaku Busshitsu Kanri Senta Nyusu, 31(4), p.6 - 9, 2002/04
no abstracts in English
C, and its application to surface and soil airAmano, Hikaru; Koma, T.*; Atarashi-Andoh, Mariko; Koarashi, Jun; Iida, Takao*
Journal of Radioanalytical and Nuclear Chemistry, 252(2), p.353 - 357, 2002/00
Times Cited Count：6 Percentile：39.48(Chemistry, Analytical)no abstracts in English
Tanigawa, Hiroyasu; Ando, Masami; Kato, Yudai*; Hirose, Takanori*; Sakasegawa, Hideo*; Jitsukawa, Shiro; Koyama, Akira*; Iwai, Takeo*
Journal of Nuclear Materials, 297(3), p.279 - 284, 2001/09
Times Cited Count：34 Percentile：89.94(Materials Science, Multidisciplinary)no abstracts in English
Oshima, Takayuki; Matsuda, Toshiaki; Tsugita, Tomonori; Sakata, Shinya; Sato, Minoru; Koiwa, Motonao*
Review of Scientific Instruments, 72(1), p.517 - 519, 2001/01
Times Cited Count：6 Percentile：40.19(Instruments & Instrumentation)no abstracts in English
; Nemoto, Masaaki; Saikawa, Takuya*; Sukegawa, Kazuya*
JNC TN9410 2000-008, 66 Pages, 2000/03
JNC-TN9410-2000-008.pdf:1.39MB
The experimental fast reactor "JOYO" served as the MK-II irradiation bed core for testing fuel and material for FBR development for 15 years from 1982 to 1997. During the MK-II operation, impurities concentrations in the sodium and the argon gas were determined by 67 samples of primary sodium, 81 samples of secondary sodium, 75 samples of primary argon gas, 89 samples of secondary argon gas (the overflow tank) and 89 samples of secondary argon gas (the dump tank). The sodium and the argon gas purity control data were accumulated from in thirty-one duty operations, thirteen special test operations and eight annual inspections. These purity control results and related plant data were compiled into database, which were recorded on CD-ROM for user convenience. Purity control data include concentration of oxygen, carbon, hydrogen, nitrogen, chlorine, iron, nickel and chromium in sodium, concentration of oxygen, hydrogen, nitrogen, carbon monoxide, carbon dioxide, methane and helium in argon gas with the reactor condition.
JNC TJ4420 2000-002, 794 Pages, 2000/03
JNC-TJ4420-2000-002.pdf:23.42MB
no abstracts in English
