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Mohamad, A. B.; Nakajima, Kunihisa; Miwa, Shuhei; Osaka, Masahiko
Journal of Nuclear Science and Technology, 60(3), p.215 - 222, 2023/03
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)Aihara, Jun; Ueta, Shohei; Goto, Minoru; Inaba, Yoshitomo; Shibata, Taiju; Ohashi, Hirofumi
JAEA-Technology 2018-002, 70 Pages, 2018/06
JAEA-Technology-2018-002.pdf:1.46MB
HTFP code is code for calculation of additional release amount of fission product (FP) from fuel rod in high temperature gas-cooled reactor (HTGR) after stop of fission. Minory changed Fornax-A code also can calculate that. Therefore, release behavior of Cs calculated with HTFP code was compared with that calculated with minory modified FORNAX-A code in this report. Release constants of Cs evaluated with minory modified FORNAX-A code are rather different from default values for HTFP code.
Miyahara, Naoya; Miwa, Shuhei; Nakajima, Kunihisa; Osaka, Masahiko
Proceedings of 2017 Water Reactor Fuel Performance Meeting (WRFPM 2017) (USB Flash Drive), 9 Pages, 2017/09
This paper presents the development of a reproductive experimental setup for FP release and transport and an analysis tool considering chemical reaction kinetics for the construction of the FP chemistry database. The performance test of the reproductive experimental setup TeRRa using CsI compounds show that TeRRa can reproduce well a FP chemistry-related behavior such as aerosol formation, growth and deposition behavior. An analytical tool has been developed based on the commercial ANSYS-FLUENT code. Some additional models was added to evaluate detailed FP chemistry during release and transport in this study. A test analysis simulating the CsI heating test in steam atmosphere was carried out to demonstrate the performance of the improved code. The result shows the appropriateness of the additional models.
Yamane, Yuichi; Amano, Yuki; Tashiro, Shinsuke; Abe, Hitoshi; Uchiyama, Gunzo; Yoshida, Kazuo; Ishikawa, Jun
Journal of Nuclear Science and Technology, 53(6), p.783 - 789, 2016/06
Times Cited Count：6 Percentile：43.12(Nuclear Science & Technology)The release behavior of radioactive materials from high active liquid waste (HALW) has been experimentally investigated under boiling accident conditions. In the experiments using HALW obtained through laboratory scale reprocessing, release ratio was measured for the FP nuclides such as Ru, 
Tc, Cs, Sr, Nd, Y, Mo, Rh and actinides such as 
Cm, 
Am. As a result, the release ratio was 0.20 for Ru and 1
for the FP and Ac nuclides. Ru was released into the gas phase in the form of both mist and gas. For its released amount, weak dependency was found to the initial concentration in the test solution. The release ratio decreased with the initial concentration. For other FP nuclides and actinides as non-volatile, released into the gas phase in the form of mist, the released amount increased with the initial concentration. The release ratio of Ru and NOx concentration increased with temperature of the test solutions. They were released almost at the same temperature between 200 and 300
C. Size distribution of the mist and other particle was measured.
Di Lemma, F. G.; Miwa, Shuhei; Osaka, Masahiko
JAEA-Review 2016-007, 27 Pages, 2016/03
JAEA-Review-2016-007.pdf:1.88MB
During a nuclear power plant Severe Accident, complex boron melts can be formed, due to interaction of the control rods with the cladding materials. These can affect ultimately the source term assessment. This review will describe the results of previous studies on boron carbide/stainless steel/Zircaloy (B
C/SS/Zry) melts, which will finally provide guidance for the needs of future experiments. This review showed that models for the behavior of complex BC/SS/Zry melts are limited, and unsuccessful in simulating core degradation, thus the improvement of the database for BC/SS/Zry melts is needed. Our experimental plan aims in providing thermodynamics and kinetics models for such melts, with the final aim of improving boron modelling in SA codes analysis and of understanding its effect on fission products behavior.
Aihara, Jun; Ueta, Shohei; Nishihara, Tetsuo
JAEA-Technology 2015-040, 32 Pages, 2016/02
JAEA-Technology-2015-040.pdf:0.83MB
Original FORNAX-A is a calculation code for amount of fission product (FP) released from fuel rods of pin-in-type high temperature gas-cooled reactors (HTGRs). This report is for explanation what calculations become possible with minor changed FORNAX-A.
Nomoto, Yasunobu; Aihara, Jun; Nakagawa, Shigeaki; Isaka, Kazuyoshi; Ohashi, Hirofumi
JAEA-Data/Code 2015-008, 39 Pages, 2015/06
JAEA-Data-Code-2015-008.pdf:10.32MB
HTFP is a calculation code for amount of additionally released fission product (FP) from fuel rods of pin-in-type according to transient of core temperature at the accident of high temperature gas-cooled reactors (HTGRs). This code analyzes FP release inventory from core according to the transient of core temperature at the accident as an input data and considering FP release rate from a fuel compact and a graphite sleeve and radioactive decay of FP. This report describes the outline of HTFP code and its input data. The computed solutions using the HTFP code were compared to those of HTCORE code, which was used for the design of the High Temperature Engineering Test Reactor (HTTR) to validate the analysis models of the HTFP code. The comparison of HTFP code results with HTCORE code results showed the good agreement.
Sawa, Kazuhiro; Ueta, Shohei; Sumita, Junya; Verfondern, K.*
Journal of Nuclear Science and Technology, 38(6), p.411 - 419, 2001/06
Times Cited Count：17 Percentile：74.75(Nuclear Science & Technology)no abstracts in English
Nakamura, Takehiko; Hidaka, Akihide; Kudo, Tamotsu; Hayashida, Retsu*; Otomo, Takashi; Nakamura, Jinichi; Uetsuka, Hiroshi
JAERI-Conf 2000-015, p.201 - 209, 2000/11
no abstracts in English
Nakamura, Takehiko; Hidaka, Akihide; Hashimoto, Kazuichiro; Harada, Yuhei; Nishino, Yasuharu; Kanazawa, Hiroyuki; Uetsuka, Hiroshi; Sugimoto, Jun
JAERI-Tech 99-036, 34 Pages, 1999/03
no abstracts in English
Tobita, Tsutomu; Minato, Kazuo; Sawa, Kazuhiro; Fukuda, Kosaku; Sekino, Hajime; Iida, Shozo;
JAERI-Research 96-014, 34 Pages, 1996/03
JAERI-Research-96-014.pdf:2.15MB
no abstracts in English
J.Yan*; Maruyama, Yu; Sugimoto, Jun
JAERI-Tech 95-052, 27 Pages, 1995/12
no abstracts in English
Sawa, Kazuhiro; Tanaka, Toshiyuki
JAERI-Research 95-071, 23 Pages, 1995/11
JAERI-Research-95-071.pdf:0.53MB
no abstracts in English
; ; Iwai, Takashi; Saito, Junichi; Nakagawa, Tetsuya; Oyamada, Rokuro; Saito, Minoru
JAERI-M 93-016, 0, p.259 - 267, 1993/02
no abstracts in English
Matsumoto, Mikio; Endo, Yasuichi; ; Itabashi, Yukio; ; Yokouchi, Iichiro; Ando, Hiroei
JAERI-M 92-212, 62 Pages, 1993/01
no abstracts in English
CMinato, Kazuo; Ogawa, Toru; Fukuda, Kosaku; Sekino, Hajime; ; ;
Journal of Nuclear Materials, 202, p.47 - 53, 1993/00
Times Cited Count：60 Percentile：96.91(Materials Science, Multidisciplinary)no abstracts in English
Sawa, Kazuhiro; Shiozawa, Shusaku; Fukuda, Kosaku;
Journal of Nuclear Science and Technology, 29(9), p.842 - 850, 1992/09
no abstracts in English
; Saito, Minoru; Oyamada, Rokuro; ; ; Saito, Junichi; Iwai, Takashi; ; Nakagawa, Tetsuya
Nucl. Saf., 33(3), p.334 - 343, 1992/07
no abstracts in English
Sawa, Kazuhiro; Murata, Isao; Shindo, Ryuichi; Shiozawa, Shusaku
JAERI-M 91-198, 58 Pages, 1991/11
no abstracts in English
Sawa, Kazuhiro; Shiozawa, Shusaku; Shindo, Masami; Tazawa, Yujiro*; *; *; *;
JAERI-M 91-158, 69 Pages, 1991/10
no abstracts in English
