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Tanaka, Tadao; Mukai, Masayuki; Maeda, Toshikatsu; Matsumoto, Junko; Ogawa, Hiromichi; Munakata, Masahiro; Kimura, Hideo; Bamba, Tsunetaka; Fujine, Sachio
Genshiryoku eye, 49(2), p.76 - 79, 2003/02
no abstracts in English
Noguchi, Hiroshi; Yokoyama, Sumi*
KURRI-KR-80, p.50 - 56, 2002/08
no abstracts in English
Ohtaki, Akira; ; ; *; *;
JNC TN9410 2000-006, 74 Pages, 2000/04
JNC-TN9410-2000-006.pdf:3.01MB
To evaluate materials balance in nuclear fuel cycle quickly and quantitatively the fuel cycle requirement code "FAMILY" was improved. And an accumulated TRU&LLFP quantity analysis code was developed. The contents are as follows: (1)A calculation ability of minor actinide production and expenditure was added to the "FAMILY" code. (2)An output program for the "FAMILY" calculation results was developed. (3)A simple version of "FAMILY" code was developed. (4)An analysis code for accumulated TRU&LLFP quantity in nuclear fuel cycle was developed.
;
JNC TN9400 2000-034, 48 Pages, 2000/03
JNC-TN9400-2000-034.pdf:1.56MB
The study and the development to put FBR (Fast Breeder Reactor) to practical use have been doing. So many kinds of technologies are investigated to construct nuclear fuel recycle received to the society. The most important aim of reprocessing has been to extract U and Pu from spent fuels effectively, but, now, the demands for reprocessing are many kinds on nuclear fuel recycle system's construction. These need to be accepted sufficiently. The system that consists of electrolysis, extraction, with molten salt and melting metal, volatilization and condensation using the difference of vapor pressure is suggested, because, differently from LWR (Light Water Reactor), FBR can use the low decontamination factor's fuel. When the engineering scale plant is designed, the dry reprocessing has unsolved problems(ex. process flow) because of less demonstrative scale plants of the dry reprocessing than ones of the wet reprocessing. So the analysis and the estimation of mass balance that is most fundamental in the dry reprocessing system's design need to keep up with the system's alteration (to add new processes etc.) flexibly. This study aim is to develop the mass balance estimation code of dry reprocessing that satisfies the demand mentioned above.
Takase, Kazuyuki; Kunugi, Tomoaki*; Seki, Yasushi; Akimoto, Hajime
Nuclear Fusion, 40(3Y), p.527 - 535, 2000/03
Times Cited Count：11 Percentile：34.93(Physics, Fluids & Plasmas)no abstracts in English
Kurihara, Ryoichi; Seki, Yasushi; Ueda, Shuzo; Aoki, Isao; Nishio, Satoshi; Ajima, Toshio*; Kunugi, Tomoaki; Takase, Kazuyuki; Yamauchi, Michinori*; *; et al.
Journal of Fusion Energy, 16(3), p.225 - 230, 1997/00
Times Cited Count：3 Percentile：30.34(Nuclear Science & Technology)no abstracts in English
Miyasaka, Yasuhiko
Enerugi Rebyu, 15(9), p.11 - 15, 1995/00
no abstracts in English
RIST News, (20), p.12 - 19, 1995/00
no abstracts in English
Togawa, Orihiko
Hoken Butsuri, 28, p.67 - 69, 1993/00
no abstracts in English
Shimooke, Takanori; ;
Nihon Genshiryoku Gakkai-Shi, 22(4), p.223 - 230, 1980/00
Times Cited Count：0 Percentile：0.02(Nuclear Science & Technology)no abstracts in English
Takahashi, Fumiaki; Manabe, Kentaro; Sato, Kaoru; Tokashiki, Yuji*
no journal, ,
If national radiation safety regulations are revised by adapting the concept of the ICRP 2007 Recommendations, the protection standard values are also reviewed for radiation exposure. Thus, JAEA has developed an internal dosimetry code based on the ICRP 2007 Recommendations since FY 2017. Two functions are to be incorporated to the codes. One is "dose coefficient calculation function" that is used to verify the new dose coefficients by ICRP and the other is "nuclide intake estimation function" for internal dosimetry monitoring. In addition, we have developed GUI to set up calculation condition and functions to indicate results. In the dose coefficient calculation function, a user can set up internal dosimetry model based upon the 1990 recommendation to investigate the influencing factors on a difference between the old and new dose coefficients. In addition, results such as in-vivo radioactivity are also displayed with a graph in the nuclide intake estimation function. We will report an overview of the beta version of the code that integrates the two functions.
Takahashi, Fumiaki; Manabe, Kentaro; Sato, Kaoru
no journal, ,
The International Commission on Radiological Protection (ICRP) has published dose coefficients for internal exposure dose evaluation in accordance with dose assessment methods in the 2007 Recommendations based on newly obtained findings. In the future, if the policy of ICRP 2007 Recommendation is incorporated into national radiation regulations, standards for internal exposure protection are to be revised based on the new coefficients. Therefore, JAEA has developed an internal dose assessment code to verify whether the dose coefficient published by the ICRP has been accurately derived from fundamental dosimetry models and data or not, through a project commissioned by the Nuclear Regulatory Agency. The code also implements functions for radiation dose management and emergency dose assessment at each site based on the 2007 Recommendations. In this presentation, we will report the outline of the beta version of the code developed and examples of its application.
Takahashi, Fumiaki
no journal, ,
The current regulations for radioisotopes have been enacted based on the 1990 Recommendations of the International Commission on Radiological Protection (ICRP) in Japan. On the other hand, ICRP has published the 2007 Recommendations and then discussions are underway to incorporate the new Recommendations into Japanese radiation regulations. In addition, the international standard model and data used have been updated for internal dosimetery by ICRP. Thus, if the 2007 Recommendations of ICRP are incorporated into domestic radiation regulations, the regulatory standard values may be updated for internal exposure. In this presentation, reviews will be made on the latest dose assessment model and data based on the 2007 Recommendations of ICRP, focusing on changes from the past ones. Next, we will report on the internal exposure dose evaluation code that is being developed as a commissioned project from the Nuclear Regulation Authority.
Nishihara, Kenji; Takeshita, Kenji*; Shimada, Takashi*; Nakase, Masahiko*
no journal, ,
Many codes have been developed in the world to quantify future nuclear scenarios for the purpose of developing nuclear energy utilization strategies and R&D goals. However, quality assurance and verification of the accuracy of the codes are not yet fully implemented, with only simple benchmark intercomparisons by the OECD/NEA. In the various evaluation codes, many models are used for each process of the nuclear fuel cycle and nuclear reactors, and there are differences in the definitions of inputs and outputs and databases, so a general verification method has not been established. Therefore, we developed a verification and validation (V&V) method for quantity evaluation codes to contribute to quality assurance and accuracy verification in the future.
