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CsUchiyama, Yusuke*; Tokunaga, Natsuki*; Azuma, Kohei*; Kamidaira, Yuki; Tsumune, Daisuke*; Iwasaki, Toshiki*; Yamada, Masatoshi*; Tateda, Yutaka*; Ishimaru, Takashi*; Ito, Yukari*; et al.
Science of the Total Environment, 816, p.151573_1 - 151573_13, 2022/04
Times Cited Count：7 Percentile：68.71(Environmental Sciences)no abstracts in English
Matsuda, Norihiro; Konno, Chikara; Ikehara, Tadashi; Okumura, Keisuke; Suyama, Kenya*
JAEA-Data/Code 2020-003, 33 Pages, 2020/03
JAEA-Data-Code-2020-003.pdf:1.85MB
Data handling modules for the radioactivity calculation code, ORIGEN-S, are developed for the reliable evaluations of radioactivity inventory. By using these modules, an activation cross-section data library for the ORIGEN-S code is updated easily and effectively based on a facility-specific neutron spectrum and multi-group neutron activation cross-section library for decommissioning of nuclear facilities, MAXS2015. In order to guarantee the reliability of the radioactivity calculations, functions of data verification in a visual way and numerical comparison between before and after the data processing are also prepared.
C values of organic matter in surface sediments off Saru River in northern Japan, one year after a flood event in 2006Nagao, Seiya*; Irino, Tomohisa*; Aramaki, Takafumi*; Ikehara, Ken*; Katayama, Hajime*; Otosaka, Shigeyoshi; Uchida, Masao*; Shibata, Yasuyuki*
Radiocarbon, 52(3), p.1068 - 1077, 2010/08
Times Cited Count：0 Percentile：0.01(Geochemistry & Geophysics)This study discusses the effects of flooding on the spatial distribution of organic matter on the shelf region of off the Saru River, southern part of Hokkaido, Japan, on the basis of the C and 
C values. Surface sediments on the shelf were collected in August 2007, one year after the severe flood in 2006. Suspended particles and sediment of the Saru River were also collected in August 2007 and 2008. The C values of organic matter in the shelf sediments ranged from -665 to -77 per mil. The silt and clay sediments had C values of -240 to -77 per mil, but the sandy sediments ranged from -665 to -388 per mil. The values of particulate organic carbon in the Saru River are -292 to -247 per mil at normal flow conditions. These results indicate that surface soil with relatively older organic matter is deposited on the shelf region by the flooding event, and freshly-produced organic matter in sea surface is deposited after the flooding.
Kobayashi, Kensuke*; Goto, Daisuke*; Tojo, Masayuki*; Ikehara, Tadashi*; Kaji, Yoshiyuki; Nemoto, Yoshiyuki
no journal, ,
We evaluate fuel temperature based on the steady state heat transfer analysis with considering accurate fuel history and storage conditions.
Tada, Kenichi; Ikehara, Tadashi; Ono, Michitaka*; Tojo, Masayuki*
no journal, ,
Comparison of the nuclear data processing code is realised using nuclear data processing code FRENDY which has been developed in JAEA. In this study, we compared the difference of the nuclear data processing codes between FRENDY and NJOY. The impact of difference between open nuclear data processing codes on neutron transport calculations were also investigated. In this presentation, the difference of the nuclear data processing method between FRENDY and NJOY and ACE verification project carried out by IAEA.
Ono, Michitaka*; Tojo, Masayuki*; Tada, Kenichi; Ikehara, Tadashi
no journal, ,
The difference of the nuclear data processing affects the difference of cross section library and neutronics calculation. This presentation explains the comparisons of the cross section libraries and neutronics calculation results.
Tada, Kenichi; Ikehara, Tadashi; Ono, Michitaka*; Tojo, Masayuki*
no journal, ,
JAEA develops a nuclear data processing code FRENDY. We can comparison and verification of conventional nuclear data processing code using FRENDY. In this presentation, we focus on the thermal scattering law data. We found some problems of NJOY to process the thermal scattering law data as follows, (1) The generation of input file is complex and we found some inputting error in the official ACE library, (2) The maximum energy of ACE file is not identical to the inputted maximum energy, (3) If user uses iwt=2 option in ACER module, MCNP6.1 cannot treat this generated ACE file appropriately and the calculation will not completed This presentation explains the overview of these problems.
Ono, Michitaka*; Tojo, Masayuki*; Tada, Kenichi; Ikehara, Tadashi
no journal, ,
JAEA develops a nuclear data processing code FRENDY. We can compare and verify the conventional nuclear data processing code using FRENDY. In this presentation, we explain the impact of the difference of the nuclear data processing codes on the neutronics calculations using MCNP.
Tokashiki, Mikio*; Ikehara, Tadashi*; Tada, Kenichi; Egawa, Toru*; Yokoyama, Kenji; Iwamoto, Osamu
no journal, ,
The bias factor methods have been widely used for applications to reduce uncertainties of the predicted value in the reactor physics characteristics. In the present study, an attempt has been made to apply the extended bias factor method to qualifying the reliability of measured data by assuming the uncertainty of the numerical model being negligible and the covariance of cross section being reliable. In this presentation, comparison results will be shown between actual measured value and the predicted value of a benchmark case sampled from the benchmark suite. Furthermore, it will be shown that the comparison and their uncertainty enable us to qualify the degree of reliability of the actual measured value.
