Report of Tokai Works  PNCT-AR-68

[目次]

  • CONTENTS
  • NUCLEAR FUEL RESEARCH LABORATORY
  • Ceramics Group
  • 1. Buffering of UC(I) EMF Measurement of Uranium Activity in the U-C System / 1
  • 2. Ultrasonic Measurement in Sintered UO2-U4O9 Pellets / 3
  • 3. Frictional Force of Dislocation in Uranium Oxide / 4
  • 4. Preparation of Uranium Carbide by Carbothermic Reduction / 5
  • 5. Preparation of UO2 Microspheres by the Sol-Gel Process / 6
  • 6. Compatibility of Some Cladding Materials with UO2 and UC / 8
  • 7. Alpha-Autoradiography by Using Cellulose Nitrate / 10
  • 8. In-Core Irradiation Test of Vibratorily Compacted Sol-Gel UO2 in JRR-2 / 12
  • Reprocessing Group
  • 9. Oxidation and Reduction of Tri and Tetravalent Plutonium in Nitric Acid Solution / 15
  • 10. Redox Reactions of Tri and Tetravalent Plutonium in Nitric Acid Solutions by Controlled Potential Coulometric Method / 17
  • 11. Reduction of Hexavalent Plutonium in Nitric Acid Solutions with Nitrous Acid or Hydrogen Peroxide / 18
  • 12. Process Study for Aqueous Reprocessing(VI)Proving Test of U-Purification Cycle / 20
  • 13. Process Study for Aqueous Reprocessing(V)Modification of Plutonium Purification Process using Nitrous Acid / 21
  • 14. Process Study for Aqueous Reprocessing(VII)Improvement of Decontamination Factor in a Codecontamination Process / 22
  • 15. Distribution of U(VI)Ions between Several Inorganic Ion Exchangers and Nitric Acid Solutions / 23
  • 16. Characteristics of the Bench-Scale Pilot Plant for Treatment of Low-Level Radioactive Waste / 25
  • 17. Removal of Radioactive Strontium from Low-Level Radioactive Liquid Waste by Coagulation / 27
  • 18. Removal of Cs and Sr in Low-Level Radioactive Wastes by Phenolic Ion Exchange Resins / 29
  • 19. Treatment of Liquid Wastes Containing Fission Products by Coagulation-Precipitation / 31
  • 20. Solubility of Krypton and Xenon in Some Solvents / 32
  • Other Groups
  • 21. Corrosion of FRP in Uranium Hexafluoride / 34
  • 22. Nuclear Kinetics of Annular Enriched Fuel and Special Annular Enriched Fuel / 35
  • 23. Performance of Annular Enriched Fuel and Special Annular Enriched Fuel / 36
  • 24. Characteristics of Uranium Minerals in Tōnō Area / 37
  • 25. Geochemical Study for Uranium Deposit in Hata,Mitoya-cho,Shimane-Prefecture / 37
  • PLUTONIUM FUELS DIVISION
  • Fuel Design Section
  • 26. Experimental Study on the Consequences of Fuel Cladding Failure-Part IV / 39
  • 27. Design,Fabrication and Inspection of Grids and Spacers for HBWR Irradiation Assembly(IFA-160) / 41
  • 28. Design and Fabrication of Grids and Their Assessment Studies / 42
  • 29. PuO2-UO2 Critical Experiment(4)A Measurement for Decay Characteristic of Fission Product γ Ray of PuO2-UO2 Fuel / 43
  • 30. PuO2-UO2 Critical Experiment(5)Critical Experiment and Analysis of Power Distribution for IFA-159 / 45
  • 31. Design and Safety Analysis of the Capsule Containing PuO2-UO2 Fuel for IRT Irradiation Testing in the GETR / 48
  • 32. PuO2-UO2 Critical Experiment(V)Fine Thermal Neutron Flux Distribution in the PuO2-UO2 Fuel Rods in Hard Spectrum / 50
  • Fuel Preparation Section
  • 33. Preparation of the UO2-PuO2 for the HALDEN IFA-160 Irradiation Test by Sol-Gel Process / 52
  • 34. Preparation of PuO2-UO2 Mixed Oxide by Sol-Gel Process / 53
  • 35. Fabrication of UO2-PuO2 Irradiation Test Samples for Halden-160 / 54
  • 36. Fabrication of the UO2-PuO2 Irradiation Test Samples for Thermal Reactor Use / 55
  • 37. Recovery of Plutonium by Anion Exchange Method / 56
  • 38. Plutonium Waste Disposal / 57
  • Testing and Analysis Section
  • 39. Thermal Expansion of(Pu-U)O2-x / 59
  • 40. Thermal Diffusivity Measurements of UO2-x and(Pu-U)O2 by a Modulated Electron Beam Technique / 60
  • 41. Post-Irradiation Examination and Analysis of PuO2-UO2 Fuel Specimens for the Screening Irradiation Testing in GETR / 62
  • 42. Structure Change of Fuel Irradiated in GETR-2 / 63
  • 43. Structure Change of Fuel Irradiation in GETR-1-Void Ratio Distribution Change / 64
  • 44. An Analytical Method for the Determination of Plutonium in PuO2-UO2 by Gamma-Spectrometry / 66
  • 45. Behaviour of Fission Products in UO2 and PuO2-UO2(I) / 66
  • 46. Some Observations on Moisture and Released Gas in PuO2-UO2 / 68
  • 47. Measurements of PuO2 Particles in PuO2-UO2 by Using XMA and PDM / 70
  • 48. Phase Study on U-Pu-O System(II) / 72
  • TECHNOLOGY DIVISION
  • Analysis Section
  • 49. Direct Spectrophotometric Determination of Trace Amounts of Uranium by TAM / 73
  • 50. Chemical Behaviour of Pu in Sea Water / 74
  • 51. Mass Spectrometry of Sulfur Hexafluoride / 76
  • 52. Plutonium Analysis by Mass Spectrometry(I)A Trial Manufacture of a Glove Box and a Sample-Loading Apparatus / 78
  • 53. Plutonium Analysis by Mass Spectrometry(II)Determination of Isotopic Composition of Plutonium / 79
  • Fuel Inspection Section
  • 54. Assembling Technique and Inspection Procedure for Experimental Fast Reactor Fuel Assembly(I)(Fox-C-2) / 81
  • 55. Studies on Assembling Technique and Inspection Procedure of Fast Experimental Reactor Fuel Assembly(II)(FCRE-11) / 83
  • 56. Wall Thickness Measurements of Zircaloy Tubing by Using Ultrasonic Thickness Tester / 84
  • 57. Biaxial Creep-Rupture Tests of Austenitic Stainless Steel Cladding / 85
  • HEALTH AND SAFETY SECTION
  • 58. Observation of Plutonium Contaminated Materials by an Autoradiographic Technique / 86
  • 59. Test of Filter Systems with DOP Aerosol. / 87
  • 60. An Air Proportional Survey Meter for Plutonium Contamination Control / 88

「国立国会図書館デジタルコレクション」より

この本の情報

書名 Report of Tokai Works
著作者等 動力炉核燃料開発事業団
シリーズ名 PNCT-AR ; 67-68
巻冊次 PNCT-AR-68
出版元 Tokai Works, Power Reactor & Nuclear Fuel Development Corporarion
刊行年月 1969
ページ数 2冊
大きさ 30cm
全国書誌番号
22056718
※クリックで国立国会図書館サーチを表示
言語 英語
出版国 日本
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