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Kiyanagi, Yoshiaki*; Kino, Koichi*; Furusaka, Michihiro*; Hiraga, Fujio*; Kamiyama, Takashi*; Kato, Kiyoshi*; Igashira, Masayuki*; Katabuchi, Tatsuya*; Mizumoto, Motoharu*; Oshima, Masumi; et al.
Journal of the Korean Physical Society, 59(2), p.1781 - 1784, 2011/08
Times Cited Count：13 Percentile：62.11(Physics, Multidisciplinary)The project of the comprehensive nuclear data research for the development of the advanced reactor systems had been executed successfully by eight organizations from 2005 to 2009. In this project, we constructed the pulsed neutron beamline that was aimed to obtain neutron capture cross-sections of long-lived fission products and minor actinides accurately. The energy spectra, spatial distributions, and pulses of the beam were studied by measurements and simulation calculations, and they were found to be consistent with those of the beamline design. In this paper, we present the overview of the project and the properties of the neutron beam provided by this beam line.
Yonehara, Hidenori*; Ishimori, Yuu; Akiba, Suminori*; Iida, Takao*; Iimoto, Takeshi*; Kai, Michiaki*; Shimo, Michikuni*; Tokonami, Shinji*; Yamada, Yuji*; Yoshinaga, Shinji*; et al.
Hoken Butsuri, 42(3), p.201 - 213, 2007/09
The pooled analysis recently carried out in European countries and North American countries showed the excess relative risk of lung cancer increased by 10-20% per 100 Bqm
increase in indoor radon concentration. The Scientific Committee on Indoor Radon Risk and Response to the Issue established by the Japan Health Physic Society reviewed the scientific evidence on the indoor radon risk obtained so far and evaluated the pooled analysis results from the viewpoint of estimating the risk coefficient in Japan. The committee concludes that the risk shown by the pooled analysis results has the consistency from miners risk analysis, and that it is probably not low in the reliability and validity, although the value may include the uncertainties caused from the correction of radon concentration measured, from the effect of thoron on measurement results, from the differences of environmental parameters in exposure, and so on.
Yamada, Susumu*
JNC TJ8400 2001-047, 61 Pages, 2002/02
JNC-TJ8400-2001-047.pdf:1.99MB
In this trust fund, we reviewed sucriticality measuring methods and neutron or gamma ray measuring and date transmission systems appropriate for realizing inexpensive on-line criticality surveillance systems, which is required for ensuring the safety of nuclear fuel reprocessing plants. Since the neutron flux level in subcritical systems is fairly low without external neutron sources, it is desirable to use pulse type neutron detectors for subcritical measurement systems. This logically implies that subcriticality measurement methods based on the temporal domain should be used for developing an on-line criticality surveillance system. In the deep subcriticality conditions, a strong external neutron source is needed for reactivity measurement and a D-T tube can be used in order to improve the accuracy of the measurement. A D-T tube is convenient since it is free from Tritium problem since Tritium is sealed in an airtight container and also can be controlled by power supply. Hence, under deep subcritical conditions, Feynman-
or Rossi- method should be used. On the contrary, under sallow subcriticality conditions where high neutron counting is expected, we can use current type neutron detectors and a recursive ARMA model identification approach or a digital reactivity meter method for sucriticality measurement. For neutron or gamma ray detection and data transmission systems to develop a reliable critical surveillance system, we propose to use plastic scintillation glass fiber cable. Since this cable can transmit the right signal more than twenty meters, this cable can be applied in such a way of surrounding the outside of the fuel resolving tank.
Yamada, Susumu*
JNC TJ8400 2001-003, 87 Pages, 2001/02
JNC-TJ8400-2001-003.pdf:4.47MB
In view of necessity and importance of criticality surveillance systems for ensuring the safety of nuclear fuel manufacturing and reprocessing plants, 5-year basic studies and 4-year R&D studies on an on-line criticality surveillance system were carried out since 1991. This report is a summary of these series of studies. Noticing that the signal from a neutron detector is random in principle, these series of studies aimed to accumulate knowledge for developing an inexpensive criticality surveillance system with quick response based on the Auto-Regressive Moving Average (ARMA) model identification algorithm. During five-year basic studies on criticality surveillance system since 1991, we obtained knowledge required for developing a criticality surveillance system based on the ARMA model identification algorithm through (1)studies on recursive ARMA model identification algorithms most appropriate for estimating subcriticality form time series data under a steady state condition, (2)studies on pre-processing of signal from neutron detectors, (3) developing a new recursive ARMA model identification algolithm with small time delay to estimate time-dependent subcriticality, (4) proposing a basic concept for the elements required for an on-line criticality surveillance system, and (5) numerical analysis of data from the DCA experiments. During next four-year R&D studies on a criticality surveillance system since 1996, we (1) proposed modules required for a no-line criticality surveillance system, (2) revealed effectiveness of a adaptive digital filter (ADF) algorithm, as an important redundancy to the recursive ARMA model identification algorithm to be used in the signal processing module through numerical analysis of real data, (3) proposed a module of the Feynman- method over 
ray signal and a fast signal processing module for ray signal, (4)devdoped a line-noise removal filter(Notch filter) and revealed its effectiveness for the DCA ...
Yamada, Susumu*
JNC TJ8400 2000-051, 122 Pages, 2000/02
JNC-TJ8400-2000-051.pdf:2.15MB
Developing an inexpensive on-line criticality surveillance system is required for ensuring the safety of nuclear fuel reprocessing plants. Based on the series of researches for five years, R&D study on On-line Criticality Surveillance System has been carricd out since 1996. The concept of this Criticality Surveillance System is based on the Auto-Regressive Moving Average (ARMA) model identification algorithms to the time series of signal fluctuation of a neutron detector. We have proposed several new ideas of modification to the original design of the Criticality Surveillance System, and also reported some results of numerical analysis over the DCA experiments. In those days, DOS/V personal computers with Microsoft Windows have came into wide use instead of those based on the MS-DOS, which have been popular in Japan. NEC, a major maker of MS-DOS computers, stopped the production of MS-DOS computers and changed their management policy toward production of DOS/V personal computers. Our researches have been developed using MS-DOS computers. For the effective use of these important results, it became an urgent theme to transplant all programs developed on MS_DOS computers into computers with the OS, which is not easily affected by commercialism. Since the design concept should be based on high reliability, electromagnetic disturbance-free and high expandability, and also computers have achieved remarkably high performance as well as low price in these days, these computers should be used not only as a simple signal processing unit but also a totally integrated signal analyzing system along with conventional signal analyzing software in stead of IC chips with analyzing soft wares. This configuration enables us to easily introduce newly developed techniques and to provide supplement information. Then, this approach can enhance the reliability of the Criticality Surveillance System without addition of any special devices, and also provide the flexibility of ...
*; *; *; *; *; Kojima, Takuji; *
Nuclear Instruments and Methods in Physics Research A, 311, p.498 - 504, 1992/00
Times Cited Count：17 Percentile：81.26(Instruments & Instrumentation)no abstracts in English
Se(,n) reaction by using LCS -rayKitatani, Fumito; Harada, Hideo; Oshima, Masumi; Utsunomiya, Hiroaki*; Kaihori, Takeshi*; Yamada, Kawakatsu*; Toyokawa, Hiroyuki*; Kiyanagi, Yoshiaki*
no journal, ,
no abstracts in English
