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Matsuo, Yoichiro*; Izumi, Yoshinobu*; Hase, Yoshihiro; Sakamoto, Ayako; Shimizu, Kikuo*
JAEA-Review 2015-022, JAEA Takasaki Annual Report 2014, P. 104, 2016/02
no abstracts in English
Matsuo, Yoichiro*; Izumi, Yoshinobu*; Hase, Yoshihiro; Sakamoto, Ayako; Shimizu, Kikuo*
JAEA-Review 2014-050, JAEA Takasaki Annual Report 2013, P. 119, 2015/03
no abstracts in English
Matsuo, Yoichiro*; Izumi, Yoshinobu*; Hase, Yoshihiro; Sakamoto, Ayako; Nozawa, Shigeki; Narumi, Issey*; Shimizu, Kikuo*
JAEA-Review 2013-059, JAEA Takasaki Annual Report 2012, P. 112, 2014/03
Matsuo, Yoichiro; Sasaki, Shinji
JAEA-Review 2013-007, 46 Pages, 2013/05
Radioactive corrosion products (CP) are main cause of personal radiation exposure during maintenance without fuel failure in FBR plants. The most important CP species are Mn and
Co. The deposited radioactive CP cause radiation fields near the piping and components. Then, the deposited radioactive CP contributes to the radiation exposure of the plant-worker. In this review, firstly, collects knowledge about CP transfer behavior in the fast reactor and analyzes it and organize essence of the CP transfer behavior. Secondly, existing method to parse CP transfer behavior is investigated and extracts the issues and discusses it about the solution of those issues. Finally, about a specific example of the improvement based on the solution, a recent trend is investigated and describes evaluated content.
Matsuo, Yoichiro*; Izumi, Yoshinobu*; Hase, Yoshihiro; Sakamoto, Ayako; Nozawa, Shigeki; Narumi, Issei; Shimizu, Kikuo*
JAEA-Review 2012-046, JAEA Takasaki Annual Report 2011, P. 105, 2013/01
Matsuo, Yoichiro; Miyahara, Shinya; Izumi, Yoshinobu*
Journal of Power and Energy Systems (Internet), 6(1), p.6 - 17, 2012/03
Radioactive corrosion product (CP) is a main cause of personal radiation exposure during maintenance with no breached fuel in fast breeder reactor (FBR) plants. In order to establish techniques of radiation dose estimation for radiation workers in radiation-controlled areas of the FBR, the PSYCHE (Program SYstem for Corrosion Hazard Evaluation) code was developed. We add the Particle Model to the conventional PSYCHE analytical model. In this paper, we performed calculation of CP transfer in JOYO using an improved calculation code in which the Particle Model was added to the PSYCHE code. The C/E (calculated / experimentally observed) value for CP deposition was improved through use of this improved PSYCHE code incorporating the Particle Model.
Matsuo, Yoichiro*; Izumi, Yoshinobu*; Hase, Yoshihiro; Sakamoto, Ayako; Nozawa, Shigeki; Narumi, Issei; Shimizu, Kikuo*
JAEA-Review 2011-043, JAEA Takasaki Annual Report 2010, P. 108, 2012/01
Matsuo, Yoichiro; Hasegawa, Masanori; Maegawa, Yoshiharu; Miyahara, Shinya
Hoken Butsuri, 46(4), p.304 - 313, 2011/12
Radioactive corrosion products (CP) are main source of personal radiation exposure during maintenance without fuel-failure accident in the liquid-metal fast breeder reactor (LMFBR) plants. In order to establish the techniques of radiation dose estimation for personnel, program system DORE has been developed. The DORE system is constructed by PSYCHE code and QAD code system. The density of each deposited CP of primary coolant system in MONJU was estimated by using the PSYCHE. Moreover, the QAD-CGGP2R code is applied to dose rate calculations for the primary coolant system in MONJU. The predicted values were estimated to be saturated at 2-3 mSv/h in twenty years after the start of operation, and the dose rate reaches 4 mSv/h in domains near the IHX and the cold-leg piping.
Matsuo, Yoichiro; Miyahara, Shinya; Izumi, Yoshinobu*
Proceedings of 19th International Conference on Nuclear Engineering (ICONE-19) (CD-ROM), 8 Pages, 2011/10
In order to establish the techniques of radiation dose estimation for worker in radiation-controlled area, PSYCHE code has been developed. The PSYCHE is based on the Solution-Precipitation model. The CP transfer calculation using the Solution-Precipitation model needs a fitting factor for the calculation of the precipitation of CP. In this study, in addition to existing Solution-Precipitation model in PSYCHE, a transfer-model of CP species in particle form was applied to calculations of CP behavior in the primary cooling system of fast breeder reactor MONJU. Based on the calculated results, we estimated the contribution of CP deposition in the particle-form. It was suggested that the improved model including transfer-model of CP species in particle-form could be used for evaluation of CP transfer and radiation-source distribution in place of conventional Solution-Precipitation model with fitting factor in the PSYCHE.
Shimizu, Kikuo*; Matsuo, Yoichiro*; Izumi, Yoshinobu*; Hase, Yoshihiro; Nozawa, Shigeki; Sakamoto, Ayako; Narumi, Issei
JAEA-Review 2010-065, JAEA Takasaki Annual Report 2009, P. 79, 2011/01
Matsuo, Yoichiro; Hasegawa, Masanori; Maegawa, Yoshiharu; Miyahara, Shinya
Journal of Power and Energy Systems (Internet), 5(1), p.96 - 107, 2011/01
Radioactive corrosion products (CP) are primary cause of personal radiation exposure during maintenance work at FBR plants with no breached fuel. The PSYCHE code has been developed based on the solution-precipitation model for analysis of CP transfer behavior. We predicted and analyzed the CP solution and precipitation behavior of MONJU to evaluate the applicability of the PSYCHE code to MONJU, using the parameters verified in the calculations for JOYO. From the calculation result pertaining to the MONJU system, distribution of Mn deposited in the primary cooling system over 20 years of operation is predicted to be approximately 7 times larger than that of
Co. In particular, predictions show a notable tendency for
Mn precipitation to be distributed in the primary pump and cold-leg. The calculated distribution of
Mn and
Co in the primary cooling system of MONJU agreed with tendencies of measured distribution of JOYO.
Matsuo, Yoichiro; Hasegawa, Masanori; Maegawa, Yoshiharu; Miyahara, Shinya
Proceedings of 18th International Conference on Nuclear Engineering (ICONE-18) (CD-ROM), 8 Pages, 2010/05
Radioactive corrosion products are main cause of personal radiation exposure during maintenance with no breached fuel in FBR plants. CP is produced in the core region by activation of fuel cladding and sub-assembly wrappers, and they are transported to the primary circuit with sodium flow and deposited on the wall of the primary piping and components. In order to establish the techniques of radiation dose reduction for of personnel, program system for corrosion hazard evaluation code PSYCHE has been was developed. The PSYCHE code is based on the solution-precipitation model. The density of each deposited CP and dose rate of primary coolant system in Monju was estimated by using the PSYCHE and QAD-CG code.
Matsuo, Yoichiro*; Nishijima, Shigehiro*; Hase, Yoshihiro; Nozawa, Shigeki; Sakamoto, Ayako; Narumi, Issei; Shimizu, Kikuo*
JAEA-Review 2009-041, JAEA Takasaki Annual Report 2008, P. 75, 2009/12
no abstracts in English
Matsuo, Yoichiro*; Nishijima, Shigehiro*; Hase, Yoshihiro; Sakamoto, Ayako; Narumi, Issei; Shimizu, Kikuo*
JAEA-Review 2008-055, JAEA Takasaki Annual Report 2007, P. 60, 2008/11
no abstracts in English
Matsuo, Yoichiro*; Nishijima, Shigehiro*; Hase, Yoshihiro; Sakamoto, Ayako; Yokota, Yuichiro; Narumi, Issei; Shimizu, Kikuo*
JAEA-Review 2007-060, JAEA Takasaki Annual Report 2006, P. 86, 2008/03
no abstracts in English
Matsuo, Yoichiro*; Nishijima, Shigehiro*; Hase, Yoshihiro; Sakamoto, Ayako; Tanaka, Atsushi; Shimizu, Kikuo*
JAEA-Review 2006-042, JAEA Takasaki Annual Report 2005, P. 76, 2007/02
no abstracts in English
Matsuo, Yoichiro*; Izumi, Yoshinobu*; Hase, Yoshihiro; Sakamoto, Ayako; Shimizu, Kikuo*
no journal, ,
no abstracts in English
Matsuo, Yoichiro*; Izumi, Yoshinobu*; Hase, Yoshihiro; Sakamoto, Ayako; Shimizu, Kikuo*
no journal, ,
no abstracts in English
Matsuo, Yoichiro*; Izumi, Yoshinobu*; Hase, Yoshihiro; Sakamoto, Ayako; Shimizu, Kikuo*
no journal, ,
no abstracts in English
Shimizu, Kikuo*; Matsuo, Yoichiro*; Izumi, Yoshinobu*; Nozawa, Shigeki; Hase, Yoshihiro; Sakamoto, Ayako; Tanaka, Atsushi
no journal, ,
no abstracts in English