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Journal Articles

The Suppression effect of natural barrier for the radionuclide migration under the practice environment

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

Journal Articles

Tritium dose assessment Code; ACUTRI and TRINORM

Noguchi, Hiroshi; Yokoyama, Sumi*

KURRI-KR-80, p.50 - 56, 2002/08

no abstracts in English

JAEA Reports

Expansion of material balance analysis function on nuclear fuel cycle

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.

JAEA Reports

The development of mass balance estimation code; The development and the analyzed example with object type code(I)

;

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.

Journal Articles

Thermal hydraulic characteristics during ingress of coolant and loss of vacuum events in fusion reactors

Takase, Kazuyuki; Kunugi, Tomoaki*; Seki, Yasushi; Akimoto, Hajime

Nuclear Fusion, 40(3Y), p.527 - 535, 2000/03

 Times Cited Count:8 Percentile:70.09(Physics, Fluids & Plasmas)

no abstracts in English

JAEA Reports

None

PNC-TJ1545 97-001, 328 Pages, 1997/03

PNC-TJ1545-97-001.pdf:16.07MB

no abstracts in English

JAEA Reports

None

PNC-TJ1531 97-001, 103 Pages, 1997/03

PNC-TJ1531-97-001.pdf:4.28MB

no abstracts in English

Journal Articles

Proposal of integrated test facility for in-vessel thermofluid safety of fusion reactors

Kurihara, Ryoichi; Seki, Yasushi; Ueda, Shuzo; Aoki, Isao; Nishio, Satoshi; *; Kunugi, Tomoaki; Takase, Kazuyuki; Yamauchi, Michinori*; *; et al.

Journal of Fusion Energy, 16(3), p.225 - 230, 1997/00

 Times Cited Count:2 Percentile:74.98(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Dismantling of Japan Power Demonstration Reactor (JPDR)

Miyasaka, Yasuhiko

Enerugi Rebyu, 15(9), p.11 - 15, 1995/00

no abstracts in English

Journal Articles

Evaluation methodology for seismic base isolation of nuclear equipments and computer code EBISA

RIST News, (20), p.12 - 19, 1995/00

no abstracts in English

JAEA Reports

None

*

PNC-TJ1604 93-003, 46 Pages, 1993/03

PNC-TJ1604-93-003.pdf:1.84MB

no abstracts in English

Journal Articles

Present status in development of computer codes for internal dose assessment, 3.2, DOSDAC

Togawa, Orihiko

Hoken Butsuri, 28, p.67 - 69, 1993/00

no abstracts in English

Journal Articles

Criticality safety analysis in nuclear fuel cycle

; ;

Nippon Genshiryoku Gakkai-Shi, 22(4), p.223 - 230, 1980/00

 Times Cited Count:0 Percentile:100(Nuclear Science & Technology)

no abstracts in English

Oral presentation

Development of internal dosimetry code based upon ICRP 2007 Recommendations

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.

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