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sp. AS-131 isolated from Antarctic OceanYonezawa, Yasushi*; Nagayama, Aiko*; Tokunaga, Hiroko*; Ishibashi, Matsujiro*; Arai, Shigeki; Kuroki, Ryota; Watanabe, Keiichi*; Arakawa, Tsutomu*; Tokunaga, Masao*
Protein Journal, 34(4), p.275 - 283, 2015/08
Times Cited Count：4 Percentile：11.01(Biochemistry & Molecular Biology)Nucleoside diphosphate kinase isolated from psychrophilic sp. AS-131 (ASNDK) was expressed in 
and purified to homogeneity. Comparing to mesophilic NDK isolated from 
, ASNDK exhibited highly elevated thermolability: (1) 
expression at 37
C as a denatured insoluble form, and (2) 30C lower optimum temperature of enzymatic activity. The subunit structure of ASNDK was suggested to be dimer, as in NDKs isolated from moderate halophiles.
Iwamoto, Yosuke; Fukuda, Mitsuhiro*; Sakamoto, Yukio; Tamii, Atsushi*; Hatanaka, Kichiji*; Takahisa, Keiji*; Nagayama, Keiichi*; Asai, Hiroaki*; Sugimoto, Kenji*; Nashiyama, Isamu*
Nuclear Technology, 173(2), p.210 - 217, 2011/02
Times Cited Count：30 Percentile：89.62(Nuclear Science & Technology)The 30 white neutron beam at RCNP facility has been characterized as a prove suitable for testing of single event effects (SEEs) in semiconductors in the neutron energy range from 1 to 300 MeV using the 392-MeV proton incident reaction on a 6.5-cm-thick tungsten target. The neutron spectrum in measurements were demonstrated to provide a neutron spectrum similar to the terrestrial one at sea level, but with an enhancement in the intensity of a factor of 1.5
10
. The average neutron intensity and spectrum from 10 to 300 MeV at RCNP were almost same as those at WNR. The calculated RCNP neutron flux using PHITS generally agreed with the measured RCNP data within a factor of two. As the neutron density per pulse for RCNP is 500 times lower than that for WNR, the pileup probability of single-event transient currents and false multiple-bit upsets is reduced. Such conditions at RCNP are suitable for accelerated SEE testing to get meaningful results in realistic time frame.
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.
