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Volume 43, Issue 12
Displaying 1-8 of 8 articles from this issue
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Near Future Technology Projected by JSPS-RFTF ADVENTURE ProjectShinobu YOSHIMURA2001 Volume 43 Issue 12 Pages 1185-1190
Published: December 30, 2001
Released on J-STAGE: March 08, 2010
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Akira ENDO2001 Volume 43 Issue 12 Pages 1191-1194
Published: December 30, 2001
Released on J-STAGE: March 08, 2010
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2001 Volume 43 Issue 12 Pages 1201a
Published: 2001
Released on J-STAGE: April 21, 2009
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2001 Volume 43 Issue 12 Pages 1201b
Published: 2001
Released on J-STAGE: April 21, 2009
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Kenji TAKESHITA, Yoshio NAKANO2001 Volume 43 Issue 12 Pages 1216-1219
Published: December 30, 2001
Released on J-STAGE: April 21, 2009
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Tetsuo MATSUMOTO2001 Volume 43 Issue 12 Pages 1220-1227
Published: December 30, 2001
Released on J-STAGE: April 21, 2009
JOURNAL FREE ACCESSSeveral prospective materials (neutron filter/moderator, beam reflector, gamma ray shielding and beam collimator) were studied with a view to generating thermal and epithermal neutron beams suited for boron neutron capture therapy (BNCT). The beams are delivered from the thermal and thermalizing column exits situated on two opposite faces of a TRIGA-II type reactor. An investigation was performed with Monte Carlo calculations from a viewpoint of obtaining sufficiently intense thermal and epithermal neutron beams separately, and little adulterated both with neutrons of extraneous energy ranges and with gamma rays. High-density graphite (G) would be the most suitable material for thermal neutron beams as a neutron filter/moderator, and the combination of aluminum (Al) and aluminum fluoride (AlF3) for epithermal neutron beams. The graphite would be also the most promising material for thermal neutron beams as a beam reflector while for epithermal neutron beams the choice would be lead fluoride (PbF2). The PbF2 would be also the most suitable material for epithermal neutron beams as a gamma ray shielding, and bismuth (Bi) for thermal neutron beam. The PbF2 would be also the most useful material for epithermal neutron beam as a beam collimator while for thermal neutron beam the choice would be the graphite The epithermal neutron beam for BNCT could be optimized with the progressive use of PbF2.View full abstractDownload PDF (3327K) -
Moriyasu KANARI, Tetsuya ABE, Yasuo KOSAKU, Sadamitsu TANZAWA, Seiji H ...2001 Volume 43 Issue 12 Pages 1228-1234
Published: December 30, 2001
Released on J-STAGE: April 21, 2009
JOURNAL FREE ACCESSThe adhesive strength of insulation films for fusion reactor is important from the view point in which the durability is improved. In the present study, the adhesive strength of a plasma sprayed alumina insulation film coated on the stainless steel substrate was investigated by using a repeated impact test. The impact tests were performed at 3 kinds of mean impact pressure, 3, 5 and 12 times as large as the yield strength of the substrate, about 200MPa, in 2 surface materials combinations of alumina/alumina and alumina/bear stainless steel. In the alumina/alumina combination, the durability of the alumina films were over 30, 000 cycles at the mean impact pressures of 3 and 5 times, and we confirmed sufficiently high adhesive strength of the alumina film. And the alumina/stainless combination improved the durability of the alumina film by a factor of 2.7. While at the mean impact pressure of 12 times, because the stainless steel substrate gave rise to a plastic strain being 2 orders higher than the allowable strain of the alumina films, the alumina film was fractured by the propagation of cracks.View full abstractDownload PDF (7150K) -
Shoichi TACHIMORI, Shinichi SUZUKI, Yuji SASAKI2001 Volume 43 Issue 12 Pages 1235-1241
Published: December 30, 2001
Released on J-STAGE: March 08, 2010
JOURNAL FREE ACCESSA new chemical process, ARTIST process, is proposed for the treatment of spent nuclear fuel. The main concept of the ARTIST process is to recover and stock separately all actinides, uranium and a mixture of transuranics, and to dispose fission products. The process composed of two main steps, a uranium exclusive isolation and a total recovery of transuranium elements (TRU); which copes with the nuclear non-proliferation measures, and additional processes. Both actinide products are solidified by calcination and allowed to the interim storage for future utilization. These separations are achieved by use of amidic extractants in accord with the CHON principle. The technical feasibility of the ARTIST process was explained by the experimental results of both the branched-alkyl monoamides in extracting uranium and supressing the extraction of tetravalent actinides due to the steric effect and the diglycolic amide in thorough extraction of all TRU by tridentate coordination. When these TRU are requested to put into reactors, LWR or FBR, for power generation or the Accelerator-Driven System (ADS) for transmutation, lanthanides are to be removed from TRU by utilizing a soft nitrogen donor ligand.View full abstractDownload PDF (12072K)
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