Post Irradiation Examination for The FUGEN High Burn-up MOX Fuel Assembly (III) Final Report

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.

Post Irradiation Examination for The FUGEN High Burn-up MOX Fuel Assembly (II) Destructive Examination (Part 1)

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.

Behavior of irradiated ATR/MOX fuel under reactivity initiated accident conditions

Sasajima, Hideo; Fuketa, Toyoshi; Nakamura, Takehiko; Nakamura, Jinichi; Kikuchi, Keiichi*

Journal of Nuclear Science and Technology, 37(5), p.455 - 464, 2000/05

https://doi.org/10.3327/jnst.37.455

no abstracts in English

Behavior of PWR and BWR fuels during reactivity-initiated accident conditions

Fuketa, Toyoshi; Nakamura, Takehiko; Sasajima, Hideo; Nagase, Fumihisa; Uetsuka, Hiroshi; Kikuchi, Keiichi*; Abe, Tomoyuki*

Proceedings of an International Topical Meeting on Light Water Reactor Fuel Performance (CD-ROM), 15 Pages, 2000/00

no abstracts in English

Alloying Effects on Young's Modulus and Vickers Hardness of Zirconium, and Construction of Characteristics Diagrams for Alloy Design

Shibutani, Hideo*; Morinaga, Masahiko*; *; Matsushita, Kenichi*; Kikuchi, Keiichi

Nihon Genshiryoku Gakkai-Shi, 40(6), p.501 - 508, 1998/06

https://doi.org/10.3327/jaesj.40.501

None

Nodular corrosion of zirconium alloys and XPS analysis of surface oxide layer

Shibutani, Hideo*; Morinaga, Masahiko*; Kikuchi, Keiichi

Nihon Kinzoku Gakkai-Shi, 62(6), p.534 - 541, 1998/00

None

High linear power irradiation test with Am-MOX fuels, 7; Evaluation of the thermal design aspect for FBR MOX fuels

Ikusawa, Yoshihisa; Kikuchi, Keiichi; Ozawa, Takayuki; Maeda, Seiichiro; Nakajima, Hiroshi*; Koike, Naoto

no journal, , 

To study the thermal performance of Am-MOX fuels, the high linear power irradiation test with Am-MOX fuels "B14 irradiation test" was carried out in the fast experimental reactor "JOYO". From the result of the irradiation test, the thermal performance for Am-MOX fuel was confirmed and the fuel irradiation behavior code was verified.