124 results on '"Nishitani, T."'
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2. Recent progress in blanket materials development in the Broader Approach activities
3. IFMIF specifications from the users point of view
4. Progress of IFERC project in the Broader Approach Activities
5. Impact of reflected neutrons on accuracy of tritium production rate prediction in blanket mock-ups for fusion reactors
6. Angle-correlated spectrum measurement for two neutrons emitted from (n, 2n) reaction with the coincidence detection technique using a pencil-beam DT neutron source
7. Thin slit streaming experiment for ITER by using D-T neutron source
8. Verification of nuclear data for DT neutron induced charged-particle emission reaction of light nuclei
9. Engineering design of the ITER invessel neutron monitor using micro-fission chambers
10. Search for luminescent materials under 14 MeV neutron irradiation
11. Improved in situ calibration technique for ITER ex-vessel neutron yield monitor
12. Measurements of deuteron-induced activation cross sections for IFMIF accelerator structural materials in the energy range of 22–40 MeV
13. Neutronics design of the low aspect ratio tokamak reactor, VECTOR
14. Progress in the blanket neutronics experiments at JAERI/FNS
15. Ion and neutron beam analyses of hydrogen isotopes
16. Development of CAD/MCNP interface program prototype for fusion reactor nuclear analysis
17. Activation experiment with D–T neutrons on materials relevant to liquid blankets
18. Possibility of tritium self-sufficiency in low aspect ratio tokamak reactor with the outboard blanket only
19. Analysis of sequential charged particle reaction experiments for fusion reactors
20. Measurements of deuteron-induced activation cross-sections for IFMIF accelerator structural materials
21. Photocathodes for the energy recovery linacs
22. The reduction of the change of secondary ions yield in the thin SiON/Si system
23. Deuterium depth profiling in JT-60U W-shaped divertor tiles by nuclear reaction analysis
24. Accessibility evaluation of the IFMIF liquid lithium loop considering activated erosion/corrosion materials deposition
25. Measurement of energetic charged particles produced in fusion materials with 14 MeV neutron irradiation
26. Tritium breeding experiments with blanket mock-ups containing [formula omitted]-enriched lithium titanate and beryllium irradiated with DT neutrons
27. Temperature dependence of the transmission loss in KU-1 and KS-4V quartz glasses for the ITER diagnostic window
28. Heterogeneous breeding blanket experiment with lithium titanate and beryllium
29. Analysis of neutron propagation from the skyshine port of a fusion neutron source facility
30. Direct tritium measurement in lithium titanate for breeding blanket mock-up experiments with D-T neutrons
31. Overview on materials R&D activities in Japan towards ITER construction and operation
32. Optical characteristics of aluminum coated fused silica core fibers under 14 MeV fusion neutron irradiation
33. Radiation-induced thermoelectric sensitivity in the mineral-insulated cable of magnetic diagnostic coils for ITER
34. Radiation induced conductivity of ceramic coating materials under 14 MeV neutron irradiation
35. Non-destructive analysis of impurities in beryllium, affecting evaluation of the tritium breeding ratio
36. Radioactivity of the vanadium-alloy induced by D–T neutron irradiation
37. Radiation-hardening techniques of dedicated optical fibres used in plasma diagnostic systems in ITER
38. Measurement of deuterium and tritium retentions on the surface of JT-60 divertor tiles by means of nuclear reaction analysis
39. Radiation detector made of a diamond single crystal grown by a chemical vapor deposition method
40. Electrical properties of mineral-insulated cable under fusion neutron irradiation
41. Shutdown dose evaluation experiment for ITER
42. Measurement of radiation skyshine with D–T neutron source
43. Deterioration and recovery effects in energy responses of semiconductor X-ray detectors due to nuclear-fusion produced neutron irradiation
44. Impact of armor materials on tritium breeding ratio in the fusion reactor blanket
45. In-situ irradiation test of mica substrate bolometer at the JMTR reactor for the ITER diagnostics
46. Decay heat measurement of fusion related materials in an ITER-like neutron field
47. Round-robin irradiation test of radiation resistant optical fibers for ITER diagnostic application
48. Absolute measurement of D–T neutron flux with a monitor using activation of flowing water
49. Neutron irradiation tests on diagnostic components at JAERI
50. Impact of irradiation effects on design solutions for ITER diagnostics
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