5,592 results on '"STEAM"'
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2. ORNL Nuclear Safety Research and Development program bimonthly report for January - February 1970
3. Summary Report On Design And Development Of High Temperature Gas-Cooled Power Pile
4. HRT RECOMBINER CONDENSER DESIGN
5. HRT IODINE REMOVAL BED
6. CRITICAL-ASSEMBLY EXPERIMENTS ON A REFLECTOR CONTROL SYSTEM FOR A BOILING REACTOR
7. THE EFFECT OF LOCAL BOILING ON PRESSURE DROP AND FLOW DISTRIBUTION IN THE YANKEE REACTOR CORE
8. TRANSITION BOILING HEAT TRANSFER PROGRAM. Quarterly Progress Report No. 12, October-December 1965
9. SUMMARY REPORT OF THE REACTION OF STEAM WITH LARGE SPECIMENS OF GRAPHITE FOR THE EXPERIMENTAL GAS-COOLED REACTOR
10. THE AMPLITUDE OF FLUID-INDUCED VIBRATION OF CYLINDERS IN AXIAL FLOW
11. THERMAL HYDRAULIC PERFORMANCE CHARACTERISTICS OF EBWR (0 TO 100 Mwt)
12. NATURAL CIRCULATION RECOMBINER REPORT
13. Steam reformer with catalytic combustor
14. Nuclear criticality safety study for increased enrichment limit in 2[1/2]-ton (30B) UF[sub 6] cylinders
15. THE CONSTRUCTION OF THE EXPERIMENTAL ATOMIC POWER PLANT AT KAHL
16. CONCRETE PRESSURE VESSEL FOR WYLFA
17. LOCAL BOILING PEAK HEAT FLUX FOR WATER FLOWING NORMAL TO CYLINDERS
18. A BWR FOR MERCHANT SHIP PROPULSION
19. A FACILITY USED FOR WET STEAM COOLING EXPERIMENTS: PRESSURE DROP, HEAT TRANSFER AND BURNOUT
20. CLOUD CHAMBER FOR OPTICAL MEASUREMENTS OF AEROSOLS
21. MZFR SAFETY SHIELD WITH INSTALLATION FOR PRESSURE RELEASE
22. HIGH PRESSURE GAS TUNNEL
23. STARTUP OF BOILING REACTOR VK-5 OF ULYANOVSK NUCLEAR POWER STATION
24. REACTOR TECHNOLOGY REPORT NO. 17-ENGINEERING
25. HRE-2 REPLACEMENT REACTOR STUDY NO. 2
26. STEAM GENERATOR BLOWDOWN RATE (INTERNAL INSPECTION). Test Evaluation, DLCS-3890201
27. HAZARDS SUMMARY REPORT FOR THE ARMY PACKAGE POWER REACTOR
28. HIGHLY RELIABLE CONTROL SYSTEMS FOR A 200-MW POWER REACTOR
29. Transient compressible flow in porous media
30. FORCED CONVECTION HEAT TRANSFER TO SUPERHEATED STEAM AT HIGH PRESSURE AND HIGH PRANDTL NUMBERS
31. NUCLEAR SUPERHEAT DEVELOPMENT PROGRAM. Thirteenth Quarterly Progress Report, July-September 1962
32. VESSEL AND HEAT EXCHANGER OF THE E.D.F.1 CHINON POWER PLANT
33. 20,000 KW NUCLEAR POWER PLANT STUDY FOR UNITED STATES ATOMIC ENERGY COMMISSION
34. QUARTERLY PROGRESS REPORT ON ACTIVITIES AT INSTITUTT FOR ATOMENERGI JULY- SEPTEMBER 1962
35. EFFECTS OF ELECTRICAL FIELDS ON BOILING HEAT TRANSFER. Quarterly Progress Report, April 1-June 30, 1965
36. FISSION PRODUCT RELEASE BY THE HIGH TEMPERATURE URANIUM-STEAM REACTION
37. APPROXIMATE METHOD FOR ANALYZING A NUCLEAR EXCURSION IN A LOW POWER, WATER MODERATED TEST REACTOR
38. N.T. ALPHA-S.T. ALPHA-M.T. ALPHA. THREE 65000 DWT TANKERS--A COMPARATIVE DESIGN STUDY
39. THE EFFECT OF GEOMETRIC FACTORS IN SURFACE REACTION SYSTEMS. Technical Report No. 48
40. STABILITY EXPERIMENTS FOR BOILING WATER REACTORS. Quarterly Report No. 6, April 1--June 30, 1966.
41. HEAT TRANSFER CRISIS IN STEAM-WATER MIXTURES--EXPERIMENTAL DATA IN ROUND TUBES AND VERTICAL UPFLOW OBTAINED DURING THE CAN-2 PROGRAM. Topical Report No. 11
42. EFFECTS OF ELECTRICAL FIELDS ON BOILING HEAT TRANSFER. Quarterly Progress Report, October 1, 1964-December 31, 1964
43. COMMENTS AND CORRECTIONS: ASK INFOSER
44. Steam purge of a piston/cylinder gap in a diesel engine
45. Steam boosted internal combustion engine
46. Continuous system for the treatment of coal
47. CYLINDRICAL WALL TO CONTROL THE WATER DISCHARGE AND TO CANCEL OUT THE DRIVING FORCE OF THE NATURAL CIRCULATION IN A BOILING WATER REACTOR
48. IMPROVEMENTS IN OR RELATING TO NUCLEAR REACTORS
49. AUTOMATIC FILTRATION EQUIPMENT
50. LIFTING GRIP FOR THE FUEL ELEMENTS OF A NUCLEAR REACTOR
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