45 results on '"Nishitani, T."'
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2. IFMIF specifications from the users point of view
3. Progress of IFERC project in the Broader Approach Activities
4. Impact of reflected neutrons on accuracy of tritium production rate prediction in blanket mock-ups for fusion reactors
5. Thin slit streaming experiment for ITER by using D-T neutron source
6. Verification of nuclear data for DT neutron induced charged-particle emission reaction of light nuclei
7. Engineering design of the ITER invessel neutron monitor using micro-fission chambers
8. Improved in situ calibration technique for ITER ex-vessel neutron yield monitor
9. Measurements of deuteron-induced activation cross sections for IFMIF accelerator structural materials in the energy range of 22–40 MeV
10. Neutronics design of the low aspect ratio tokamak reactor, VECTOR
11. Progress in the blanket neutronics experiments at JAERI/FNS
12. Ion and neutron beam analyses of hydrogen isotopes
13. Development of CAD/MCNP interface program prototype for fusion reactor nuclear analysis
14. Activation experiment with D–T neutrons on materials relevant to liquid blankets
15. Possibility of tritium self-sufficiency in low aspect ratio tokamak reactor with the outboard blanket only
16. Analysis of sequential charged particle reaction experiments for fusion reactors
17. Accessibility evaluation of the IFMIF liquid lithium loop considering activated erosion/corrosion materials deposition
18. Measurement of energetic charged particles produced in fusion materials with 14 MeV neutron irradiation
19. Tritium breeding experiments with blanket mock-ups containing [formula omitted]-enriched lithium titanate and beryllium irradiated with DT neutrons
20. Temperature dependence of the transmission loss in KU-1 and KS-4V quartz glasses for the ITER diagnostic window
21. Heterogeneous breeding blanket experiment with lithium titanate and beryllium
22. Direct tritium measurement in lithium titanate for breeding blanket mock-up experiments with D-T neutrons
23. Electrical properties of mineral-insulated cable under fusion neutron irradiation
24. Shutdown dose evaluation experiment for ITER
25. Measurement of radiation skyshine with D–T neutron source
26. In-situ irradiation test of mica substrate bolometer at the JMTR reactor for the ITER diagnostics
27. Absolute measurement of D–T neutron flux with a monitor using activation of flowing water
28. Neutron irradiation tests on diagnostic components at JAERI
29. Fission-reactor-radiation-tests of MI-cables and magnetic coils for fusion burning plasma diagnostics
30. Irradiation effects on magnetic probes made of mineral insulated cable
31. Results from Monte Carlo simulations of the neutron transport for the new 2.45 MeV neutron time-of-flight spectrometer for the JT-60U tokamak
32. Tritium breeding experiments with blanket mock-ups containing Li6-enriched lithium titanate and beryllium irradiated with DT neutrons
33. Measurement of energetic charged particles produced in fusion materials with 14MeV neutron irradiation
34. Japanese contribution to ITER task of irradiation tests on diagnostics components
35. Feedback control of neutron emission rate in JT-60U
36. Triton burnup measurements using scintillating fiber detectors on JT-60U
37. Development of 14 MeV neutron spectrometer for fusion experimental reactor
38. First measurements of triton burnup neutron spectra using a natural diamond detector on JT-60U
39. Design of ITER neutron yield monitor using microfission chambers
40. Invited paper: Interaction between RF and edge plasma during ICRF heating in JT-60
41. Comparative studies of the dW/dt effect in the net heating power for ignition analyses
42. The JT-60 diagnostic system
43. Conceptual design of neutron diagnostic systems for fusion experimental reactor
44. Performance of the JT-60 ICRF antenna with an open type Faraday shield
45. Thermal neutron measurement by single crystal CVD diamond detector applied with the pulse shape discrimination during deuterium plasma experiment in LHD
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