Résultats de la recherche

1

Boric acid corrosion of light water reactor pressure vessel materials /

Washington, DC : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2005

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2

Mechanism and estimation of fatigue crack initiation in austenitic stainless steels in LWR environments /

par Chopra, O. K.
Washington, DC : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2002

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3

Crack growth rates of irradiated austenitic stainless steel weld heat affected zone in BWR environments /

Washington, DC : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2006

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4

Assessment of void swelling in austenitic stainless steel core internals /

par Chung, H. M.
Washington, DC : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2006

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5

An assessment of visual testing /

par Cumblidge, S. E.
Washington, DC : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2004

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6

Irradiation-assisted stress corrosion cracking behavior of austenitic stainless steels applicable to LWR core internals /

par Chung, H. M.
Washington, DC : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2006

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7

Environmental effects on fatigue crack initiation in piping and pressure vessel steels /

par Chopra, O. K.
Washington, DC : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2001

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8

Assessment of age-related degradation of structures and passive components for U.S. nuclear power plants /

Washington, DC : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2000

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9

Review of the margins for ASME code fatigue design curve : effects of surface roughness and material variability /

par Chopra, O. K.
Washington, DC : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2003

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10

Fatigue analysis of components for 60-year plant life

Washington, DC : The Office : [Supt. of Docs., U.S. G.P.O., distributor], 2000

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11

Testing of dc-powered actuators for motor-operated valves

par DeWall, K. G.
Washington, DC : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1999

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12

Irradiation-assisted stress corrosion cracking of model austenitic stainless steels irradiated in the Halden reactor

par Chung, H. M.
Washington, DC : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1999

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13

Improved embrittlement correlations for reactor pressure vessel steels

par Eason, E. D. (Ernest D.)
Washington, DC : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1998

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14

Results of crack-arrest tests on irradiated A 508 class 3 steel

par Iskander, S. K.
Washington, DC : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1998

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15

Assessment of age-related degradation of structures and passive components for U.S. nuclear power plants

Washington, DC : U.S. Nuclear Regulatory Commission : [Supt. of Docs., U.S. G.P.O., distributor, 2000

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16

RR-PRODIGAL a model for estimating the probabilities of defects in reactor pressure vessel welds /

par Chapman, O. J. V.
Washington, DC : Washington, DC : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission ; Supt. of Docs., U.S. G.P.O. [distributor], 1998

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17

The Effect of aging at 343C on the microstructure and mechanical properties of type 308 stainless steel weldments

Washington, DC : U.S. Nuclear Regulatory Commission : [Supt. of Docs., U.S. G.P.O., distributor, 2000

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18

Residual stresses and associated stress intensity factors in core shroud weldments

Washington, DC : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1999

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19

$Assessment of the fracture behavior of weld material in full-thickness clad beams$

Assessment of the fracture behavior of weld material in full-thickness clad beams

Washington, D.C. : The Division, 1999

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20

Evaluation of WF-70 weld metal from the Midland Unit 1 reactor vessel

Washington, DC : The Office : [Supt. of Docs., U.S. G.P.O., distributor], 2000

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