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Report of Tokai Works
PNCT-AR-67
[目次]
- CONTENTS
- NUCLEAR FUEL RESEARCH LABORATORY
- Ceramics Group
- 1. The Effects of Chloride Ions and U(VI)Ions in the Sol-Gel Process of UO2 / 1
- 2. Densification Mechanism of Sol-Gel UO2 in Sintering Process / 1
- 3. The Sol-Gel Process Starting from Uranyl Nitrate Solutions / 3
- 4. A Modified Sol-Gel Process Using Fine UO2 Powder as a Starting Material / 4
- 5. Low Temperature Sintering of UO2 Pellets from the Active Powders Prepared by Hydrolysis of Uranous Solution / 5
- 6. Preparation of UC Aggregates by the Application of the Sol-Gel Process / 6
- 7. Preparation of Uranium Monocarbide Pellet / 6
- 8. Some Improvements of Sol-Gel UO2 Preparation Technology / 7
- 9. Vibratory Compaction of Sol-Gel UO2 in a Thermal Reactor Fuel Rod / 8
- 10. Fabrication of a Thermal Reactor Fuel Rod by Vib-Swaging Process / 9
- 11. Preparation of Non-Stoichiometric Uranium Dioxide / 10
- 12. Ultrasonic Attenuation in Sintered UO2 Pellets with Excess Oxygen / 11
- 13. Oxidation Behaviours of Uranium Carbides / 13
- 14. Observation of Etch Pits in Uranium Oxides / 13
- 15. Thermal Conductivity of UO2±x by Using a Transient Technique / 16
- 16. Lattice and Grain-Boundary Diffusion of Protactinium in ThO2 and ThO2-UO2 / 18
- 17. The Release of Xe-133 from Irradiated UO2 by the Step-Way Heating at Intervals of 50℃ / 18
- 18. Irradiation Testing of Vibratory Compacted Natural UO2 Prepared by the Sol-Gel Process-Post-Irradiation Examination- / 19
- Reprocessing Group
- 19. The Fundamental Distribution Data of Plutonium between Tri-n-butyl Phosphate and Nitric Acid / 21
- 20. Process Study for Aqueous Reprocessing(I)-Experimental Installation and Operation Test- / 22
- 21. Process Study for Aqueous Reprocessing(II)-Extraction Test of U-HNO3 and Pu-HNO3 Systems- / 23
- 22. Process Study for Aqueous Reprocessing(III)-Computer Evaluation of Plutonium Purification Process with TBP- / 24
- 23. Process Study for Aqueous Reprocessing(IV)-Test of U/Pu Partition Process with U(IV)as a Reductant- / 25
- 24. Recovery of Krypton and Xenon in the Off-Gases from Reprocessing of Spent Fuels.
- (I) The Solubility of Various Gases in Carbon Tetrachloride / 26
- 25. Recovery of Krypton and Xenon in the Off-Gases from Reprocessing of Spent Fuels.
- (II) Dynamic Adsorption of Krypton by Activated Carbon / 27
- 26. Use of Zeolites on the Treatment of Low-Level Radioactive Liquid Waste / 28
- Other Groups
- 27. The Uranium(IV)-(VI)Electron Exchange Reactions in the Anion Exchange Resin,Tri-n-Octyl Amine and Tri-Butyl Phosphate / 30
- 28. Behavior of Uranium Isotope in Breakthrough Operation / 32
- 29. Geochemical Characteristics of Tōno Uranium Deposits / 33
- 30. Radioactivity in Shakanai Black Ore Mine / 33
- PLUTONIUM FUEL DIVISION
- Fuel Design Section
- 31. Design and Specification of IFA-159 PuO2-UO2 Fuel Assembly for the Irradiation in HBWR / 34
- 32. Design and Specifications of IFA-159 PuO2-UO2 Fuel Assembly for the Irradiation in the Halden Boiling Water Reactor / 34
- 33. Experimental Studies for Basic Reactor Physics of PuO2-UO2 Fuel
- 1) Reactivity Effect of the Single Fuel Rod / 35
- 34. Experimental Studies for Basic Reactor Physics of PuO2-UO2 Fuel
- 2) Measurement of Fine Thermal Neutron Flux Distribution in the Single Fuel Rod / 35
- 35. Experimental Studies for Basic Reactor Physics of PuO2-UO2 Fuel
- 3) Theoretical Analysis of Fine Thermal Neutron Flux Distribution in the Single Fuel Rod / 36
- 36. Experimental Studies for Basic Reactor Physics of PuO2-UO2 Fuel
- 4) Measurement of Time Decay of Fission Product Activity / 36
- 37. Fuel Design for Plutonium Recycling in Boiling Water Power Reactor(II)Vipac Type Fuel / 37
- 38. Development of Transient Temperature Calculation Code / 37
- 39. In-Core Measurement of Thermal Conductivity of Vipac UO2 Fuel / 38
- 40. Experimental Study on the Consequences of Fuel Cladding Failure(II) / 38
- 41. Theoretical Analysis of Thermal Conductivity for Porous Ceramic Fuel / 39
- Fuel Development Section
- 42. The Irradiation Testing Program in Enrico-Fermi Fast Breeder Reactor(III)Production of Fuel Materials / 39
- 43. PuO2-UO2 Pellet Fabrication(II) / 40
- 44. Preparation of UO2-PuO2 Pellets for the Irradiation Testing in Halden HBWR / 41
- 45. PuO2-UO2 Hollow Pellet Fabrication / 41
- 46. Fabrication of PuO2-UO2 Fuel Specimens for the Screening Irradiation Test in GETR / 43
- 47. Fabrication of Enrico-Fermi Reactor Irradiation Test Specimen by Vibratory Compaction / 44
- 48. Preparation of Plutonium Hydroxide Gel by the Sol-Gel Process / 44
- 49. Preparation of High Density and Coarse Particles of UO2-PuO2 by the Sol-Gel Process / 44
- 50. Preparation of PuO2-UO2 Dense Oxide by the Sol-Gel Process(IV)-Preparation of High Plutonium Enriched PuO2-UO2- / 45
- 51. Thermal Conductivity of UO2±x / 45
- 52. Phase Study on U-Pu-O System(I) / 45
- 53. X-Ray Diffraction Work for Plutonium Oxides(II) / 46
- 54. Electron Microscopic Replica Technique for Plutonium Bearing Oxides / 46
- 55. Determination of Plutonium Distribution in PuO2-UO2 Fuel by Autoradiography-Photometry / 46
- 56. Analysis of Released Gas from UO2-PuO2 / 47
- 57. Radiochemical Determination of Isotopic Ratio in Plutonium / 47
- 58. Determination of Plutonium by Potentiometric Titration / 48
- 59. Determination of Plutonium in Waste Solution from Production Process / 48
- 60. Analysis of Impurities in PuO2 and PuO2-UO2 by Emission Spectrography / 48
- TECHNICAL DIVISION
- Analytical Section
- 61. Spectrochemical Determination of Calcium in Plutonium and Uranium Mixed Oxide / 49
- 62. Spectrophotometric Determination of Trace Amounts of Uranium by Divenzoylmethane / 50
- 63. Analytical Methods for Routine Analysis in Chemical Reprocessing Study(I) / 51
- 64. Measurement of U-235 by Microwave Discharge Method / 52
- 65. Spectrophotometric Determination of Vanadium in Uranium Oxides with N-Benzoylphenylhydroxylamin / 54
- Inspection Section
- 66. Ultrasonic Testing of Zircaloy Sheath Tubing / 54
- 67. Ultrasonic Testing of Zircaloy Sheath Tubing after Autoclave Treatment / 57
- Production Section
- 68. Fabrication Experience of Natural Uranium Thin Plate-Type Fuels for Fast Critical Assembly(I)Casting of Slabs to be Rolled / 58
- HEALTH AND SAFETY SECTION
- 69. A Use of Glass Dosimeters for Personnel Monitoring in Plutonium Facilities / 59
- 70. Local Ventilation Device Used in Plutonium Safety Handling / 60
- 71. Problems of Plutonium Contamination Control / 61
- 72. Control of Airborne Contamination in the Plutonium Fuel Development Laboratory at P.N.C. / 61
「国立国会図書館デジタルコレクション」より
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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
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巻冊次 |
PNCT-AR-67
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出版元 |
Tokai Works, Power Reactor & Nuclear Fuel Development Corporarion |
刊行年月 |
1968 |
ページ数 |
2冊 |
大きさ |
30cm |
全国書誌番号
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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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