46 results on '"Hidaka, Akihide"'
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2. Effectiveness re-evaluation on the intentional primary system depressurization during Zion-like Westinghouse PWR station blackout considering pressure dependence of radionuclides release
3. The formation mechanism of radiocesium-bearing microparticles derived from the Fukushima Daiichi nuclear power plant using electron microscopy
4. Correction: the formation mechanism of radiocesium-bearing microparticles derived from the Fukushima Daiichi nuclear power plant using electron microscopy
5. Effect of B4C Absorber Material on Melt Progression and Chemical Forms of Iodine or Cesium under Severe Accident Conditions
6. Radio-tellurium released into the environment during the complete oxidation of fuel cladding, containment venting and reactor building failure of the Fukushima accident
7. Development of the source term PIRT based on findings during Fukushima Daiichi NPPs accident
8. Sensitivity Analysis of Ex-Vessel Corium Coolability Models in MAAP5 Code for the Prediction of Molten Corium–Concrete Interaction after a Severe Accident Scenario
9. Identification of Carbon in Glassy Cesium-Bearing Microparticles Using Electron Microscopy and Formation Mechanisms of the Microparticles
10. Identification of Carbon in Glassy Cesium-Bearing Microparticles Using Electron Microscopy and Formation Mechanisms of the Microparticles.
11. 環境モニタリングデータとWSPEEDIコードで逆算した福島第一原子力発電所事故時ソースタームの131I/137Cs比を用いた事故後期の131I及び137Cs放出挙動に関する考察
12. Formation mechanisms of insoluble Cs particles observed in Kanto district four days after Fukushima Daiichi NPP accident
13. Japan - IAEA Joint Nuclear Energy Management School 2016
14. Examination of 131I and 137Cs releases during late phase of Fukushima Daiichi NPP accident by using 131I/137Cs ratio of source terms evaluated reversely by WSPEEDI code with environmental monitoring data
15. Estimation of the Release Time of Radio-Tellurium During the Fukushima Daiichi Nuclear Power Plant Accident and Its Relationship to Individual Plant Events.
16. 訂正; 環境モニタリングデータとWSPEEDIコードで逆算した福島第一原子力発電所事故時ソースタームの131I/137Cs比を用いた事故後期の131I及び137Cs放出挙動に関する考察、2017年日本原子力学会欧文誌、図6の縦軸の修正
17. ICONE23-2009 OUTLINES OF JAEA'S INSTRUCTOR TRAINING PROGRAM AND FUTURE PROSPECTS
18. Effect of B4C Absorber Material on Melt Progression and Chemical Forms of Iodine or Cesium under Severe Accident Conditions
19. Quantities of I-131 and Cs-137 in accumulated water in the basements of reactor buildings in process of core cooling at Fukushima Daiichi nuclear power plants accident and its influence on late phase source terms
20. Outcome of VEGA Program on Radionuclide Release from Irradiated Fuel under Severe Accident Conditions
21. Efforts Toward Risk Informed Regulation and Immediate Issues in Japan
22. Discussion about Further Enhancement of Logicality and Rationalization of Nuclear Regulation―Symposium on Utilization of Risk Information for Nuclear Regulation held by Nuclear Safety Commission
23. Recent Progress in Risk Consideration and Issues on Developing Risk Informed Regulations in Japan
24. Radionuclide Release from Mixed-Oxide Fuel under High Temperature at Elevated Pressure and Influence on Source Terms
25. Current Status of Utilization of Risk Information for Nuclear Regulation in Several Countries
26. Proposal of Simplified Model of Radionuclide Release from Fuel under Severe Accident Conditions Considering Pressure Effect
27. Aiming at Further Improvement of Prediction for Consequences of LWR Severe Accidents
28. Decrease of Cesium Release from Irradiated UO2Fuel in Helium Atmosphere under Elevated Pressure of 1.0 MPa at Temperature up to 2,773K
29. Enhancement of Cesium Release from Irradiated Fuel at Temperature above 2,800 K
30. Decrease of Cesium Release from Irradiated UO2 Fuel in Helium Atmosphere under Elevated Pressure of 1.0 MPa at Temperature up to 2,773 K.
31. Influence of Pressure on Cesium Release from Irradiated Fuel at Temperatures up to 2,773 K
32. Revaporization of a CsI Aerosol in a Horizontal Straight Pipe in a Severe Accident Condition
33. Experimental and analytical study on aerosol behavior in WIND project
34. Evaluation of High Temperature Tensile and Creep Properties of Light Water Reactor Coolant Piping Materials for Severe Accident Analyses
35. Effect of Microstructure on Failure Behavior of Light Water Reactor Coolant Piping under Severe Accident Conditions
36. Vapor Condensation and Thermophoretic Aerosol Deposition of Cesium Iodide in Horizontal Thermal Gradient Pipes
37. Experimental analyses of iodine behavior under severe accident conditions with ART
38. Influence of thermal properties of zirconia shroud on analysis of PHEBUS FPT0 bundle degradation test with ICARE2 code
39. Findings from CSARP; Cooperative Severe Accident Research Program.
40. Recent Advances of Thermal Hydraulic Researches in Severe Accident.
41. Enhancement of CsI Aerosol Size in Superheated Steam in Reactor Piping under Severe Accidents
42. Experimental and Analytical Study on the Behavior of Cesium Iodide Aerosol/Vapor Deposition onto Inner Surface of Pipe Wall under Severe Accident Conditions
43. SCDAP/RELAP5 Analysis of Station Blackout with Pump Seal LOCA in Surry Plant
44. Small-scale component experiments of the penetration leak characterization test in the ALPHA program
45. AIRGAMMA: A computer code for quick assessment of the cloudshine deses due to accidental releases of radioactive materials.
46. Recent Progress in Risk Consideration and Issues on Developing Risk Informed Regulations in Japan
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