Search results for: Naus, D.
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1
Structural model testing for prestressed concrete pressure vessels : a study of grouted vs nongrouted posttensioned prestressing tendon systems
Authors: Naus, D.
Published: Department of Energy, [Office of Energy Technology], Oak Ridge National Laboratory ; [for sale by the National Technical Information Service], 1979Physical Description: v, 189 pages : illustrations ; 28 cm.Holdings: Loading…
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2
Monitoring of prestressed concrete pressure vessels
Authors: Naus, D.
Published: Oak Ridge National Laboratory, Engineering Technology Division ; For sale by the National Technical Information Service, 1978Physical Description: volumes : illustrations ; 28 cmHoldings: Loading…
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3
An evaluation of the effectiveness of selected corrosion inhibitors for protection of prestressing steels in PCPVs
Authors: Naus, D.
Published: [Department of Energy, Office of Energy Technology], Oak Ridge National Laboratory ; For sale by the National Technical Information Service, 1979Physical Description: iii, 63 pages : illustrations ; 28 cm.Holdings: Loading…
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4
Structural Aging Program technical progress for period January-December 1992
Authors: Naus, D.
Published: Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1993Physical Description: ix, 152 pages : illustrations ; 28 cmHoldings: Loading…
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5
Crack-arrest behavior in sen wide plates of quenched and tempered A 533 grade B steel tested under nonisothermal conditions
Authors: Naus, D.
Published: Engineering Technology Division , U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 1987Physical Description: 1 volumeHoldings: Loading…
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6
SEN wide-plate crack-arrest tests using A 533 grade B class 1 material : WP-CE test series
Authors: Naus, D.
Published: Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989Physical Description: xxix, 119 pages : illustrations ; 28 cmHoldings: Loading…
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7
Report on aging of nuclear power plant reinforced concrete structures
Authors: Naus, D.
Published: Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1996Physical Description: xx, 271 pages : illustrations ; 28 cmHoldings: Loading…
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8
An investigation of tendon sheathing filler migration into concrete
Authors: Naus, D.
Published: Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1998Physical Description: x, 74 pages : illustrations ; 28 cmHoldings: Loading…
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9
The effect of elevated temperature on concrete materials and structures : a literature review
Authors: Naus, D.
Published: Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2006Physical Description: xix, 184 pages : digital, PDF fileHoldings: Loading…Connect to online resource - All users (Federal Depository Library Program Persistant URL)
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10
Final report, assessment of potential phosphate ion-cementitious materials interactions
Authors: Naus, D.
Published: U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2007Physical Description: xiv, 72 pages : digital, PDF fileHoldings: Loading…Connect to online resource - All users (Federal Depository Library Program Persistant URL)
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11
Primer on durability of nuclear power plant reinforced concrete structures : a review of pertinent factors
Authors: Naus, D.
Published: Division of Fuel, Engineering, and Radiological Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2007Physical Description: xiv, 114 pages : digital, PDF fileHoldings: Loading…Connect to online resource - All users (Federal Depository Library Program Persistant URL)
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12
A compilation of elevated temperature concrete material property data and information for use in assessments of nuclear power plant reinforced concrete structures
Authors: Naus, D.
Published: U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2010Physical Description: 1 online resource (327 unnumbered pages) : color illustrationsHoldings: Loading…Connect to online resource - All users (Federal Depository Library Program Persistant URL)
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13
Grouted and nongrouted tendons for prestressed concrete pressue vessels.
Authors: Naus, D.J
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14
Accustic emission monitoring of steel and concrete structural elements with particular reference.
Authors: Naus, D.J
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15
Acoustic emission monitoring of intermediate pressure vessels tested under the ORNL heavy-section steel technology program.
Authors: Naus, D.J
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16
A review of the effects of radiation on microstructure and properties of concretes used in nuclear power plants
Authors: William, Kaspar, Xi, Yunping, Naus, D.
Published: United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2013Physical Description: 1 online resource (xix, 104 pages) : color illustrations.Holdings: Loading…Connect to online resource - All users (Federal Depository Library Program Persistant URL)
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17
High-temperature crack-arrest tests using 152-mm-thick SEN wide plates of low-upper-shelf base material : tests WP-2.2 and WP-2.6
Published: Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1990Other Authors: “…Naus, D.…”
Physical Description: xxviii, 115 pages : illustrations ; 28 cmHoldings: Loading…
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18
High-temperature crack-arrest behavior in 152-mm-thick SEN wide plates of quenched and tempered A 533 grade B class 1 steel
Published: Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989Other Authors: “…Naus, D.…”
Physical Description: xxvii, 125 pages : illustrations ; 28 cmHoldings: Loading…
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19
Crack-arrest behavior in SEN wide plates of low-upper-shelf base metal tested under nonisothermal conditions : WP-2 series
Published: Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1990Other Authors: “…Naus, D.…”
Physical Description: xxxv, 265 pages : illustrations ; 28 cmHoldings: Loading…
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20
A survey of repair practices for nuclear power plant containment metallic pressure boundaries
Authors: Oland, C. B.Other Authors: “…Naus, D.…”
Published: Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1998
Physical Description: xiii, 113 pages : illustrations ; 28 cmHoldings: Loading…
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Related Subjects
Nuclear power plants
Materials
Pressure vessels
Cracking
Fracture
Fracture mechanics
Nuclear pressure vessels
Reliability
Testing
Concrete
Concrete construction
Metals
Nuclear facilities
Properties
Reinforced concrete
Reinforced concrete construction
Safety measures
Steel
Brittleness
Cement
Containment
Corrosion
Corrosion and anti-corrosives
Design and construction
Deterioration
Effect of high temperatures on
Effect of radiation on
Light water reactors
Management
Microstructure