Search results for: U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Safety Technology
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41
Compressed-air and backup nitrogen systems in nuclear power plants
Authors: Hagen, E. W.
Published: The Commission, 1982Physical Description: vii, 82 pages : illustrations ; 28 cmHoldings: Loading…
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42
Evaluation of events involving service water systems in nuclear power plants
Authors: Haried, J. A.
Published: The Commission, 1982Physical Description: vii, 62 pages : illustrations ; 28 cmHoldings: Loading…
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43
Evaluation of events involving unplanned boron dilutions in nuclear power plants
Authors: Hagen, E. W.
Published: The Commission, 1982Physical Description: vii, 32 pages ; 28 cmHoldings: Loading…
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44
Evaluation of events involving decay heat removal systems in nuclear power plants
Authors: Haried, J. A.
Published: The Commission, 1982Physical Description: vii, 98 pages : illustrations ; 28 cmHoldings: Loading…
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45
Systems interaction results from the digraph matrix analysis of a nuclear power plant's high pressure safety injection systems
Authors: Sacks, I. J. (Ivan J.)
Published: The Commission, 1984Physical Description: volumes : illustrations ; 28 cmHoldings: Loading…
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46
Collection and evaluation of complete and partial losses of off-site power at nuclear power plants
Authors: Battle, R. E.
Published: Division of Safety Technology, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1985Physical Description: ix, 53 pages : illustrations ; 28 cmHoldings: Loading…
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47
Value/impact assessment for seismic design criteria : USI A-40
Authors: Coats, D. W.
Published: The Division, 1984Physical Description: xix, 119 pages : illustrations ; 28 cmHoldings: Loading…
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48
Initial guidance on digraph-matrix analysis for systems interaction studies
Authors: Alesso, H. P.
Published: The Commission, 1983Physical Description: viii, 51 pages : illustrations ; 28 cmHoldings: Loading…
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49
Water hammer, flow induced vibration and safety/relief valve loads
Authors: Valandani, P.
Published: The Division, 1984Physical Description: 1 volume (various pagings) : illustrations ; 28 cmHoldings: Loading…
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50
Evaluation of water hammer events in light water reactor plants
Published: The Commission, 1982Physical Description: 1 volume (various pagings) ; 28 cmHoldings: Loading…
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51
Evaluation of water hammer potential in preheat steam generators
Authors: Sexton, D. E.
Published: The Commission, 1982Physical Description: 41 pages in various pagings : illustrations ; 28 cmHoldings: Loading…
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52
Assessment of scale effects on vortexing, swirl, and inlet losses in large scale sump models
Authors: Padmanabhan, M. (Mahadevan), 1943-
Published: The Commission, 1982Physical Description: 74 pages in various pagings : illustrations ; 28 cmHoldings: Loading…
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53
Methodology for evaluation of insulation debris effects : containment emergency sump performance unresolved safety issue A-43
Authors: Wysocki, J.
Published: The Commission ; National Technical Information Service [distributor], 1982Physical Description: 1 volume (various pagings) : illustrations ; 28 cmHoldings: Loading…
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54
The Effect of resolution of the Millstone Point Unit 1 Systematic Evaluation Program issues on probabilistic calculations of risk
Published: The Commission, 1983Physical Description: vi, 86 pages : illustrations ; 28 cmHoldings: Loading…
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55
Buoyancy, transport, and head loss of fibrous reactor insulation
Authors: Brocard, D. N. (Dominique N.)
Published: The Commission ; National Technical Information Service [distributor], 1982Physical Description: ix, 51 pages : illustrations ; 28 cmHoldings: Loading…
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56
Buoyancy, transport, and head loss of fibrous reactor insulation
Authors: Brocard, D. N. (Dominique N.)
Published: The Commission, 1983Physical Description: x, 59 pages : illustrations ; 28 cmHoldings: Loading…
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57
Digraph matrix analysis for systems interactions at Indian Point Unit 3
Published: Division of Safety Technology, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1986Physical Description: volumes : illustrations ; 28 cmHoldings: Loading…
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58
Review and evaluation of the Indian Point Probabilistic Safety Study
Published: The Commission, 1982Physical Description: 1 volume (various pagings) : illustrations ; 28 cmHoldings: Loading…
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59
Review of the Rancho Seco Nuclear Generating Station unit no. 1 auxiliary feedwater system reliability analysis
Authors: Ilbers, D.
Published: The Commission, 1983Physical Description: viii, 41 pages : illustrations ; 28 cmHoldings: Loading…
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60
Survey and evaluation of system interaction events and sources
Published: Division of Safety Technology, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1985Physical Description: 2 volumes : illustrations ; 28 cmHoldings: Loading…
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Related Subjects
Safety measures
Nuclear power plants
Nuclear reactors
Pressurized water reactors
Boiling water reactors
Mathematical models
Testing
Containment
Loss of coolant
Nuclear facilities
Reliability (Engineering)
System analysis
Emergency core cooling systems
Evaluation
Light water reactors
Accidents
Earthquake effects
Feed-water pumps
System failures (Engineering)
Computer programs
Control
Cooling
Design and construction
Feed-water
Fluid dynamics
Heating and ventilation
Inspection
Insulation (Heat)
Materials
Pipe lines