Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Ikusawa, Yoshihisa; Nagayama, Masahiro*
JAEA-Data/Code 2023-006, 24 Pages, 2023/07
JAEA-Data-Code-2023-006.pdf:1.42MB
Core fuels with stainless steel cladding and high plutonium content mixed oxide (MOX) fuel in a water-cooled environment, such as supercritical water-cooled reactors (SCWR) and reduced-moderation water reactors (RMWR), have been studied. In order to contribute to the research and development of such a core fuel concept, the fuel performance code "FEMAXI-8" was verified based on the results of post irradiation examinations of MOX fuel irradiated in the experimental fast reactor "JOYO". FEMAXI-8 is the latest version of the behavior analysis code developed by JAEA to analyze the behavior of light water reactor fuels under normal operation and transient conditions. This latest code has been improved and developed to allow the selection of stainless steel cladding property models to analyze improved fuels such as accident tolerant fuels. The purpose of this report is to confirm the prediction accuracy of FEMAXI-8 for the irradiation behavior of the new type of core fuel that is currently being developed. As a result of the verification, it was confirmed that FEMAXI-8 has sufficient analysis accuracy for the irradiation behavior of sodium-cooled fast reactor MOX fuel with stainless steel cladding, which exceeds the plutonium content and irradiation conditions of light water reactors. In the future, the analysis accuracy of FEMAXI-8 could be improved by adopting the O/M ratio dependence of MOX fuel thermal conductivity and the irradiation behavior evaluation model at high temperature.
Yogo, Akifumi; Sato, Katsutoshi; Nishikino, Masaharu; Mori, Michiaki; Teshima, Teruki*; Numasaki, Hodaka*; Murakami, Masao*; Demizu, Yusuke*; Akagi, Takashi*; Nagayama, Shinichi*; et al.
Applied Physics Letters, 94(18), p.181502_1 - 181502_3, 2009/05
Times Cited Count：110 Percentile：94.75(Physics, Applied)Ikusawa,Yoshihisa; Kikuchi, Keiichi; Ozawa, Takayuki; Nakazawa, Hiroaki; Isozaki,Takao*; Nagayama, Masahiro*
JNC TN8410 2005-012, 113 Pages, 2005/08
JNC-TN8410-2005-012.pdf:15.2MB
The E09 fuel assembly was irradiated in the FUGEN from February 1990 to January 1997. The fuel assembly was the highest burn-up assembly in FUGEN and the pellet peak burn-up reached about 48 GWd/t. The E09 fuel assembly was transported to Japan Atomic Energy Research Institute (JAERI) Tokai in 2001. Post Irradiation Examinations (PIE) were started in July 2001, and all PIE items were completed by March 2005. The irradiation behavior of E09 MOX fuel was evaluated from the result of PIE. The major results are as follows; The integrity of E09 fuel assembly and fuel rods was confirmed. The corrosion behavior of ATR MOX fuel cladding was similar to that of LWR-UO2 fuel cladding. The central void was observed in outer ring samples irradiated with the maximum linear power over 45kW/m. A porous fine structure, similar to the rim structure seen in LWR-UO
pellet, was observed in the circumferential region of MOX pellet and around the plutonium-rich spots. The MOX fuel properties irradiated up to ~48 GWd/t, which are pellet swelling, thermal conductivity, pellet melting temperature and diffusivity of fission gas, were similar to LWR-UO fuel properties. These results will be used for CANDU-OPTION program, which is one of Russian surplus weapon plutonium disposition programs with AECL in Canada, and available for LWR plutonium recycle program in Japan.
Ikusawa,Yoshihisa; Kikuchi, Keiichi; Ozawa, Takayuki; Nakazawa, Hiroaki; Abe, Tomoyuki; Isozaki,Takao*; Nagayama, Masahiro*
JNC TN8410 2004-008, 106 Pages, 2004/10
JNC-TN8410-2004-008.pdf:25.96MB
The "E09" was irradiated in the FUGEN from February 1990 to January 1997, and its average burn-up reached 37.7GWd/t at the end of irradiation. In order to be irradiated up to high burn-up, this fuel assembly had the design improved by applying the fissile content with axial distribution, four UO- GdO
fuel rods located with MOX fuel rods and so on. The E09 fuel assembly had been cooled in the FUGEN spent fuel pool for four years after irradiation.After that, it was transported to Japan Atomic Energy Research Institute (JAERI) Tokai in 2001.Post Irradiation Examinations (PIE) were started in July 2001 at Reactor Fuel Examination Facility in JAERI, and a part of destructive examinations(Puncture examination, Ceramography, Metallography and alpha-autoradiography) were completed in March 2003. The destructive examinations will be completed by December 2004.In this report, the data obtained from destructive examinations completed in March 2003 were summarized, and the evaluation results of irradiation performance of MOX fuel and cladding were discussed. Consequently, the MOX fuel rod integrity during irradiation was confirmed from the result of the destructive PIE. These results will be used for CANDU-OPTION program, which is one of Russian surplus weapon plutonium disposition programs with AECL in Canada, and available for LWR plutonium recycle program in Japan.
Ikusawa,Yoshihisa; Kikuchi, Keiichi; Nakazawa, Hiroaki; Abe, Tomoyuki; Isozaki,Takao*; Nagayama, Masahiro*
JNC TN8410 2003-015, 251 Pages, 2004/01
JNC-TN8410-2003-015.pdf:16.07MB
The FUGEN High Burn-up MOX Fuel Assembly E09 was developed for high burn-up fuel of DATR. The E09 MOX fuel assembly was irradiated at the FUGEN from February 1990 to January 1997, and its average burn-up reached 37.7GWd/t. In order to be irradiated up to high burn-up, they had the design improved by applying the fissile content with axial distribution, four UO2-Gd2O3 fuel rods and so on. The E09 fuel assembly had been cooled in the FUGEN spent fuel pool for four years after irradiation. After that, it was transported to Japan Atomic Energy Research Institute (JAERI) Tokai Research Establishment in 2001. Post Irradiation Examinations (PIE) were started in July 2001 at Reactor Fuel Examination Facility in JAERI, and a part of destructive examinations(Puncture examination ,Metallography and Alpha Autoradiography) were completed in March 2003. In this report, the data from destructive examinations will be summarized, and evaluation results of irradiation performance will be discussed. The integrity of fuel assembly during irradiation was confirmed in the destructive PIE.
; Nakazawa, Hiroaki; ; Nagayama, Masahiro*
JNC TY8410 2003-001, 47 Pages, 2003/04
None
Ikusawa,Yoshihisa; ; Nakazawa, Hiroaki; ; *; Nagayama, Masahiro*
JNC TN8410 2003-004, 233 Pages, 2003/02
JNC-TN8410-2003-004.pdf:24.5MB
The irradiation examination on the fuel that was fabricated for the demonstration advanced thermal reactor (DATR), had been conducted in SGHWR in the U.K. and in FUGEN. The FUGEN High Burn-up MOX Fuel Assembly "E09" was developed for high burn-up fuel of DATR. The "E09" MOX fuel assembly was irradiated at the FUGEN from February 1990 to January 1997, and its average burn-up reached 37.7GWd/t. In order to be irradiated up to high burn-up, they had the design improved by applying the fissile content with axial distribution, four UO-GdO fuel rods and so on. The E09 fuel assembly had been cooled in the FUGEN spent fuel pool for four years after irradiation. After that, it was transported to Japan Atomic Energy Research Institute (JAERI) Tokai Research Establishment in 2001. Post Irradiation Examinations (PIE) were started in July 2001 at Reactor Fuel Examination Facility in JAERI, and the nondestructive examinations were completed in March 2002. The destructive examinations have been started in April 2002, and will be completed by March 2004. In this report, the data from nondestructive examinations will be summarized, and evaluation results of irradiation performance will be discussed. The integrity of fuel assembly during irradiation was confirmed in the nondestructive PIE. These results will be available for LWR MOX fuel program in Japan and for CANDU-OPTION program, which is one of Russian surplus weapon plutonium disposition programs with AECL in Canada.
Ikusawa,Yoshihisa; ; ; ; *; Nagayama, Masahiro*
JNC TN8410 2003-005, 111 Pages, 2003/01
JNC-TN8410-2003-005.pdf:58.4MB
The "E09" MOX fuel assembly was irradiated at the FUGEN from February 1990 to January 1997, and its average burn-up reached 37.7GWd/t. In order to reach high burn-up this E09 assembly had the following characteristics comparing the demonstration ATR (DATR) MOX fuel assembly. (1)Axial fissile content distribution was introduced for the E09 assembly to reduce axial power peaking. (2)Four UO-GdO fuel rods were installed in the E09 assembly to compromise power discrepancy at the beginning of irradiation in a core. After four years cooling, it was transported to Japan Atomic Energy Research Institute(JAERI) Tokai Research Establishment in 2001. Post Irradiation Examinations (PIE) were started in July 2001 at JAERI, and the nondestructive examinations were completed in March 2002. The destructive examinations have been started in April 2002, and will be completed by March 2004. In this report, the results of nondestructive examinations were summarized, and evaluation of irradiation performance was discussed. The integrity of fuel assembly during irradiation was confirmed in the nondestructive PIE. These results will be available for LWR MOX fuel program in Japan and for CANDU-OPTION program, which is one of Russian surplus weapon plutonium disposition programs with AECL in Canada.
; Nakazawa, Hiroaki; ; Nagayama, Masahiro*
JNC TY8410 2002-002, 46 Pages, 2002/10
JNC-TY8410-2002-002.pdf:0.18MB
None
Ozawa, Takayuki; Nakazawa, Hiroaki; ; Nagayama, Masahiro*
JNC TY8410 2001-002, 46 Pages, 2002/02
JNC-TY8410-2001-002.pdf:4.62MB
None
Ozawa, Takayuki; Nakazawa, Hiroaki; Abe, Tomoyuki; Nagayama, Masahiro*
JNC TY8410 2001-001, 42 Pages, 2001/10
JNC-TY8410-2001-001.pdf:1.43MB
None
