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JAEA Reports

Analytical work at NUCEF in FY 2007

Abe, Hiroyoshi; Haga, Takahisa; Fukaya, Hiroyuki; Sonoda, Takashi; Sakazume, Yoshinori; Ito, Mitsuo; Shirahashi, Koichi

JAEA-Technology 2009-008, 24 Pages, 2009/03

JAEA-Technology-2009-008.pdf:5.62MB

Analysis of the uranyl nitrate solution fuel is carried out at the analytical laboratory of NUCEF (Nuclear Fuel Cycle Engineering Research Facility), which provides essential data for operation of STACY (Static Experiment Critical Facility), TRACY (Transient Experiment Critical Facility) and the fuel treatment system. Analyzed in FY 2007 were uranyl nitrate solution fuel samples taken before and after experiments of STACY and TRACY, samples for the preparation and pulification of uranyl nitrate solution fuel in the fuel treatment system and samples for nuclear material accountancy purpose. The total number of the samples analyzed in FY 2007 was 143. This report summarizes work related to the analysis and management of the analytical laboratory in the FY 2007.

Journal Articles

Effect of wettability on bubble formation at gas nozzle under stagnant condition

Kogawa, Hiroyuki; Shobu, Takahisa; Futakawa, Masatoshi; Ahmed, B.*; Haga, Katsuhiro; Naoe, Takashi*

Journal of Nuclear Materials, 377(1), p.189 - 194, 2008/06

 Times Cited Count:12 Percentile:61.82(Materials Science, Multidisciplinary)

It is important to understand the bubble formation behavior from the viewpoint of development on the micro bubble injection method into mercury to mitigate pressure waves in mercury target for spallation neutron source. Observation of bubble formation was carried out by using the high intense X-ray from SPring-8. A thin nozzle of 100 $$mu$$m in inner diameter and 200 $$mu$$m in outer diameter was installed into the bottom of vessel filled with mercury. Helium gas was injected to mercury through the nozzle. Bubble formation behavior in mercury was compared with that in water. Bubble formation behavior in mercury was quite different from that in water; though the bubble grew contacting the inside of the nozzle in water, it grew surrounding the outside of the nozzle in mercury. It seems that the wettability between the liquid and material of the nozzle causes the difference of bubble formation. This paper will discuss about the wettability effect on the bubble generation.

JAEA Reports

Analytical work at NUCEF in FY 2006

Sakazume, Yoshinori; Aoki, Hiromichi; Haga, Takahisa; Fukaya, Hiroyuki; Sonoda, Takashi; Shimizu, Kaori; Niitsuma, Yasushi*; Ito, Mitsuo; Inoue, Takeshi

JAEA-Technology 2007-069, 44 Pages, 2008/02

JAEA-Technology-2007-069.pdf:4.55MB

Analysis of the uranyl nitrate solution fuel is carried out at the analytical laboratory of NUCEF (Nuclear Fuel Cycle Engineering Research Facility), which provides essential data for operation of STACY (Static Experiment Critical Facility), TRACY (Transient Experiment Critical Facility) and the fuel treatment system. Analyzed in FY 2006 were uranyl nitrate solution fuel samples taken before and after experiments of STACY and TRACY, samples for the preparation of uranyl nitrate solution fuel, and samples for nuclear material accountancy purpose. The total number of the samples analyzed in FY 2006 was 254. This report summarizes work related to the analysis and management of the analytical laboratory in the FY 2006.

JAEA Reports

Analytical work at NUCEF in FY 2005

Fukaya, Hiroyuki; Aoki, Hiromichi; Haga, Takahisa; Nishizawa, Hidetoshi; Sonoda, Takashi; Sakazume, Yoshinori; Shimizu, Kaori; Niitsuma, Yasushi*; Shirahashi, Koichi; Inoue, Takeshi

JAEA-Technology 2007-005, 27 Pages, 2007/03

JAEA-Technology-2007-005.pdf:1.97MB

Analysis of the uranyl nitrate solution fuel is carried out at the analytical laboratory of NUCEF (Nuclear Fuel Cycle Engineering Research Facility), which provides essential data for operation of STACY (Static Experiment Critical Facility), TRACY (Transient Experiment Critical Facility) and the fuel treatment system. Analyzed in FY 2005 were uranyl nitrate solution fuel samples taken before and after experiments of STACY and TRACY, samples for the preparation of uranyl nitrate solution fuel, and samples for nuclear material accountancy purpose. Also analyzed were the samples from raffinate treatment and its preliminary tests. The raffinate was generated, since FY 2000, during preliminary experiments on U/Pu extraction-pulification to fix the operation condition to prepare plutonium solution fuel to be used for criticality experiments at STACY. This report summarizes work related to the analysis and management of the analytical laboratory in the FY 2005.

JAEA Reports

Annual report on analytical works at NUCEF in FY 2004

Nishizawa, Hidetoshi; Fukaya, Hiroyuki; Sonoda, Takashi; Sakazume, Yoshinori; Shimizu, Kaori; Haga, Takahisa; Sakai, Yutaka*; Akutsu, Hideyuki*; Niitsuma, Yasushi; Inoue, Takeshi; et al.

JAEA-Technology 2006-007, 24 Pages, 2006/03

JAEA-Technology-2006-007.pdf:1.81MB

Analysis of the uranyl nitrate solution fuel is carried out at the analytical laboratory of NUCEF(Nuclear Fuel Cycle Engineering Research Facility), which provides essential data for operation of STACY(Static Experiment Critical Facility), TRACY(Transient Experiment Critical Facility)and the fuel treatment system. Analyzed in FY 2004 were uranyl nitrate solution fuel samples taker before and after experiments of STACY and TRACY, samples for the preparation of uranyl nitrate solution fuel, and samples for nuclear material accountancy purpose. Also analyzed were the samples from raffinate treatment and its preliminary tests. The raffinate was generated, since FY 2000, during preliminary experiments on U/Pu extraction-pulification to fix the operation condition to prepare plutonium solution fuel to be used for criticality experiments at STACY. The total number of the samples analyzed in FY 2004 was 160. This report summarizes works related to the analysis and management of the analytical laboratory in the FY 2004.

JAEA Reports

Annual report on analytical works in NUCEF in FY. 2003

Shimizu, Kaori; Gunji, Kazuhiko*; Haga, Takahisa*; Fukaya, Hiroyuki; Sonoda, Takashi; Sakazume, Yoshinori; Sakai, Yutaka*; Akutsu, Hideyuki; Niitsuma, Yasushi*; Inoue, Takeshi; et al.

JAERI-Tech 2004-078, 27 Pages, 2005/02

JAERI-Tech-2004-078.pdf:1.84MB

Analysis of the uranyl nitrate solution fuel are carried out at the analytical laboratory, NUCEF (the Nuclear Fuel Cycle Engineering Research Facility), which provide essential data for the operations of STACY (the Static Experiment Critical Facility), TRACY (the Transient Experiment Critical Facility) and the fuel treatment system.In the FY 2003, analysis of the uranyl nitrate solution fuel from STACY/TRACY on its pre- and post-operations, analysis of the uranyl nitrate solution under preparation stage for the fuel and analysis for nuclear material accountancy purpose, have been conducted. In addition, analysis on the third U/Pu extraction/separation tests among the preliminary tests to confirm adjustment condition of plutonium solution fuel for its further use at STACY from 2000, and analysis on the experiments to treat extraction waste, were conducted. A total number of analytical samples in the FY 2003 were 156.This report summarizes works related to the analysis and management of the analytical laboratory in the FY 2003.

JAEA Reports

Annual report on analytical works in NUCEF in FY. 2002

Sakai, Yutaka; Gunji, Kazuhiko; Haga, Takahisa*; Fukaya, Hiroyuki; Sonoda, Takashi; Sakazume, Yoshinori; Akutsu, Hideyuki; Niitsuma, Yasushi; Shirahashi, Koichi; Sato, Takeshi

JAERI-Tech 2004-006, 25 Pages, 2004/02

JAERI-Tech-2004-006.pdf:1.72MB

Analyses of the uranyl nitrate solution fuel are carried out at the analytical laboratory, NUCEF (the Nuclear Fuel Cycle Engineering Research Facility), which provide essential data for the operations of STACY (the Static Experiment Critical Facility), TRACY (the Transient Experiment Critical Facility) and the fuel treatment system. In the FY 2002, analyses of the uranyl nitrate solution fuel from STACY/TRACY on its pre- and post-operations, analyses of the uranyl nitrate solution under preparation stage for the fuel and analyses for nuclear material accountancy purpose, have been conducted. In addition, analyses on the preliminary tests to confirm adjustment condition of plutonium solution fuel for its further use at STACY, and analyses on the americium extraction/separation tests to provide americium for the research on high temperature chemistry of TRU, were conducted. A total number of analytical samples in the FY 2002 were 275. This report summarizes works related to the analyses and management of the analytical laboratory in the FY 2002.

JAEA Reports

Present status of chemical analysis of uranyl nitrate solution used for the criticality experiments in NUCEF

Haga, Takahisa*; Gunji, Kazuhiko; Fukaya, Hiroyuki; Sonoda, Takashi; Sakazume, Yoshinori; Sakai, Yutaka; Niitsuma, Yasushi; Togashi, Yoshihiro; Miyauchi, Masakatsu; Sato, Takeshi; et al.

JAERI-Tech 2004-005, 54 Pages, 2004/02

JAERI-Tech-2004-005.pdf:2.06MB

Criticality experiments using uranyl nitrate solution fuel are being conducted at STACY (the Static Experiment Critical Facility) and TRACY (the Transient Experiment Critical Facility) in NUCEF (the Nuclear Fuel Cycle Safety Engineering Research Facility). Chemical analyses of the solution have been carried out to take necessary data for criticality experiments, for treatment and control of the fuel, and for safeguards purpose at the analytical laboratory placed in NUCEF. About 300 samples are analyzed annually that provide various kinds of data, such as uranium concentration, isolation acid concentration, uranium isotopic composition, concentration of fission product (FP) nuclides, tri-butyl phosphoric acid (TBP) concentration, impurities in the solution fuel and so on. This report summarizes the analytical methods and quality management of the analysis for uranyl nitrate solution relating to the criticality experiments.

JAEA Reports

Annual report on analytical works in NUCEF in FY. 2001

Sakazume, Yoshinori; Gunji, Kazuhiko; Haga, Takahisa*; Fukaya, Hiroyuki; Sonoda, Takashi; Sakai, Yutaka; Niitsuma, Yasushi; Shirahashi, Koichi; Sato, Takeshi

JAERI-Tech 2002-073, 25 Pages, 2002/09

JAERI-Tech-2002-073.pdf:2.51MB

Analytical results of uranyl nitrate solution are essential data for the operation of the Static Experiment Critical Facility (STACY), the Transient Experiment Critical Facility (TRACY) and the fuel treatment system in the Nuclear Fuel Cycle Safety Engineering Research Facility (NUCEF). Analytical works were carried out for the determination of fuel characteristics before and after criticality experiments, fuel preparation and nuclear material accountancy in FY. 2001. Moreover,as to preparation of critical experiments at STACY, plutonium preliminary tests were carried out to confirm the treatment condition (characteristics of the dissolution of the mixed oxide (MOX) powder and the extraction & separation for uranium / plutonium) of plutonium nitrate solution. Analytical works were carried out on the preliminary tests. A total number of analytical samples in FY. 2001 were 322 samples.This report summarizes the data on analytical works in FY.2001.

JAEA Reports

Annual report on analytical works in NUCEF in F.Y. 2000

Tanoue, Takahiro; Gunji, Kazuhiko; Haga, Takahisa*; Fukaya, Hiroyuki; Sonoda, Takashi; Sakazume, Yoshinori; Niitsuma, Yasushi; Miyauchi, Masakatsu; Shirahashi, Koichi; Sato, Takeshi

JAERI-Tech 2001-071, 30 Pages, 2001/11

JAERI-Tech-2001-071.pdf:4.15MB

Analytical results of uranyl nitrate solution are essential data for the operation of the Static Experiment Critical Facility (STACY), the Transient Experiment Critical Facility (TRACY) and the fuel treatment system in the Nuclear Fuel Cycle Safety Engineering Research Facility (NUCEF). Analytical works were carried out for the determination of fuel characteristics before and after criticality experiments, fuel preparation and nuclear material accountancy in FY. 2000. In accordance with handling and dissolution of mixed oxide(MOX) powder in the fuel treatment system of NUCEF ,the preliminary tests for dissolution of the MOX powder in nitric acid solution have started since the end of 2000 ,after the MOX powder transfer to the NUCEF. The analytical works were carried out for the preliminary tests. A total number of analytical samples in FY. 2000 were 483 samples . This report summarizes the data on analytical works in FY.2000.

JAEA Reports

Annual report on analysis work in NUCEF in fiscal year 1998

Togashi, Yoshihiro; Miyauchi, Masakatsu; Sonobe, Tamotsu; Niitsuma, Yasushi; Nakajima, Takayuki; Haga, Takahisa*; Tanoue, Takahiro; Fukaya, Hiroyuki; Sonoda, Takashi; Sakazume, Yoshinori; et al.

JAERI-Tech 2000-032, p.25 - 0, 2000/03

JAERI-Tech-2000-032.pdf:1.45MB

no abstracts in English

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