89 results on '"failures"'
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2. Studies on the effect of defects of a pipe joint on the fatigue stress index. Test and studies on structural design standards for nuclear power piping. II
3. Studies on the peak stress index of piping elements. Test and studies on structural design standards for nuclar power piping. I
4. Steam generators for sodium-cooled fast breeder reactors. State of development and design guide
5. Some problems about safety of nuclear power station
6. Fuel rod failure of Mihama No.2 nuclear power plant
7. Fuel rod failure of Mihama No. 2 nuclear power plant
8. Exposition of conclusion led from examination of the opinions stated in the public hearing concerning the installation of Fukushima second atomic power plant
9. Fault tree and safety design
10. Some Studies on Metallurgical Behavior of Magnox Alloy, (I)
11. A STUDY ON RUPTURE PROPERTIES OF LARGE WELDED SPECIMENS OF HT70 STEEL FOR NUCLEAR PRESSURE VESSELS. IV. SOME DISCUSSIONS ON CREEP RUPTURE CONFIGURATION.
12. ON THE FATIGUE OF WC-CO ALLOYS.
13. LIMITATIONS TO USE OF VARIOUS NUCLEAR FUELS
14. SOME STUDIES ON METALLURGICAL BEHAVIOR OF MAGNOX ALLOY. II. PHENOMENA OF CAVITATION AND CRACKING DURING CREEP
15. BRITTLE FRACTURE PREVENTION IN THICK PLATES FOR NUCLEAR REACTORS.
16. STUDIES ON THE LOSS-OF-COOLANT ACCIDENT IN WATER-COOLED NUCLEAR POWER REACTORS. II.
17. THE EXPERIMENTAL RESEARCH ON THE BRITTLENESS DUE TO HEATING HISTORY IN MANUFACTURE AND THE RADIOGRAPHIC INSPECTION OF THE PART FITTED WITH A NOZZLE OF THE PRESSURE VESSEL FOR REACTOR. 2.
18. ELECTRON MICROSCOPE OBSERVATION OF FRACTURE SURFACES OF WC--Co CEMENTED CARBIDES.
19. VIBRATION AND NOISES OF A HEAT EXCHANGER.
20. Radiographic inspection of pressure vessels
21. SUMMARY SURVEY OF DETECTION AND LOCATION OF FAILED FUEL ELEMENTS.
22. ENVIRONMENTAL EFFECTS ON RADICAL SPECIES IN IRRADIATED POLY(BUTENE-1)
23. Nuclear fuel design for light water reactors
24. Fatigue of cylinders subjected to repeated pressure
25. Dynamical behavior of coiled springs
26. EFFECT OF THE DEGREE OF WORKING ON THE CREEP-RUPTURE STRENGTH OF MOLYBDENUM COMPOSITE-CAST OF HEAT-RESISTANT ALLOYS.
27. DETERIORATION OF THE PROPERTIES OF VARIOUS VULCANIZED RUBBERS BY GAMMA IRRADIATION
28. THE EXPERIMENTAL RESEARCHES ON THE BRITTLENESS DUE TO THE HEATING HISTORY IN MANUFACTURE AND THE RADIOGRAPHIC INSPECTION OF THE PART FITTED WITH NOZZLE OF THE REACTOR PRESSURE VESSEL.
29. MECHANICAL AND PHYSICAL PROPERTIES OF SOME WC--Co CEMENTED CARBIDES. 2nd REPORT. ROTATING BENDING FATIGUE TESTS OF WC--Co CEMENTED CARBIDES.
30. OXYGEN EXCHANGE REACTION BETWEEN LACTOSE AND WATER IN THE PRESENCE OF GROUP V, VI METALLIC IONS AND URANYL ION AS CATALYSTS
31. Nuclear fuel design for fast breeder reactors
32. SINTERED INTERMETALLIC COMPOUND NiAl AS HIGH TEMPERATURE MATERIAL (2nd Report)
33. A STUDY ON RUPTURE PROPERTIES OF LARGE WELDED SPECIMENS OF HT 70 STEEL FOR NUCLEAR PRESSURE VESSELS (REPORT 2). SOME ASPECTS OF ITS CREEP RUPTURE AND HIGH TEMPERATURE PROPERTIES AS SYNTHETIC Haz specimens
34. JET FORCE STRENGTH OF REACTOR CONTAINMENT VESSELS.
35. RADIATION RAILWAY SIGNALS WITH RADIOISOTOPES LOCATED ON GROUNDS AND THEIR MECHANISMS OF FAIL-SAFE OPERATIONS
36. Problems on nuclear reactor structure at elevated temperature
37. PERFORMANCE ANALYSIS OF BWR EMERGENCY CORE COOLING SYSTEM DESIGNED FOR SHIMANE NUCLEAR POWER STATION OF CHUGOKU ELECTRIC POWER COMPANY.
38. ON THE VARIOUS PROPERTIES OF VACUUM-MELTED HEAT-RESISTANT NIMONIC 80A, S816 ALLOYS AND 13% CHROMIUM STAINLESS STEEL
39. CALCULATION OF FISSION PRODUCT CONCENTRATION IN WATER AND RELEASE RATE OF RADIOACTIVITY INTO OFF-GAS IN A BOILING WATER POWER PLANT.
40. EQUIPMENT FOR DETECTING RUPTURED FUEL ELEMENTS AT THE TOKAI POWER STATION
41. COLLISION-RESISTANT STRUCTURES OF THE NUCLEAR SHIP MUTSU.
42. IN-SERVICE INSPECTION OF NUCLEAR REACTOR COOLANT SYSTEMS.
43. OBSERVATION OF OXIDATION OF INTENTIONALLY PUNCTURED DUMMY FUEL ELEMENT. STUDY ON THE BEHAVIOR OF PUNCTURED FUEL ELEMENT FOR CALDER-HALL TYPE REACTOR. PART I
44. EFFECT OF Cu ADDITIONS ON SOME PROPERTIES OF 50 WC--15 TiC--5 TaC--30 Co ALOYS.
45. EXPLOSION BY THE IRRADIATED LIQUID NITROGEN AND OXYGEN
46. STUDY OF THE PITTING MECHANISM BY MEANS OF RADIOACTIVE ISOTOPES
47. A STUDY ON RUPTURE PROPERTIES OF LARGE WELDED SPECIMENS OF HT 70 STEEL FOR NUCLEAR PRESSURE VESSELS. REPORT 3. INFLUENCE OF HEAT TREATMENT ON CREEP RUPTURE STRENGTH.
48. RELATIONS BETWEEN PROPERTIES OF WC--TiC--NbC--10 PERCENT Co ALLOYS AND CARBON CONTENT.
49. FUNDAMENTAL STUDIES FOR EMERGENCY COOLING OF REACTOR FUEL ELEMENTS. 1. STUDIES ON THE LIQUID FILM COOLING.
50. CONFIRMATION TESTS ON METHOD OF FABRICATING LEAD SHIELDS.
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