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1
Regulatory Guide 1.207 : guidelines for evaluating fatigue analyses incorporating the life reduction of metal components due to the effects of the light-water reactor environment for new reactors.
[Washington, D.C.] : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2007

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Government Document Book
2
Status report : correlation of electrical reactor cable failure with materials degradation /
by Stuetzer, Otmar M.
Albuquerque, NM : Sandia National Laboratories, 1984

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Government Document Book
3
Kerite analysis in thermal environment of fire (KATE-fire) : test results : final report /
by Nowlen, S. P.
Washington, DC : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2011

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Government Document Book
4
An evaluation of ultrasonic phased array testing for cast austenitic stainless steel pressurizer surge line piping welds /
[ashington, DC] : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2012

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Government Document Book
5
Kerite analysis in thermal environment of fire (KATE-fire) : test results : final report /
by Nowlen, S. P.
Washington, DC : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research., 2011

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Government Document Book
6
Pacific Northwest National Laboratory investigation of stress corrosion cracking in nickel-base alloys /
Washington, D.C. : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research., 2011

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Government Document Book
7
A benchmark implementation of two dynamic methodologies for the reliability modeling of digital instrumentation and control systems /
Washington, DC : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2009

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Government Document Book
8
Stress corrosion cracking in nickel-base alloys 690 and 152 weld in simulated PWR environment - 2009 /
Washington, DC : U.S. Nuclear Regulatory Commission, Office of Nuclear Rgulatory Research, 2012

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Government Document Book
9
Final report, assessment of potential phosphate ion-cementitious materials interactions /
by Naus, D.
Washington, DC : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2007

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Government Document Book
10
Dynamic reliability modeling of digital instrumentation and control systems for nuclear reactor probabilistic risk assessments /
Washington, DC : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2007

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Government Document Book
11
Draft regulatory guide DG-1144 : guidelines for evaluating fatigue analyses incorporating the life reduction of metal components due to the effects of the light-water reactor environment for new reactors.
[Washington, D.C.] : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2008

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Government Document Book
12
Draft Regulatory Guide DG-1203 : containment performance for pressure loads.
[Washington, D.C.] : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2008

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Government Document Book
13
Rod bundle heat transfer test facility description /
Washington, D.C. : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2010

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Government Document Book
14
Rod bundle heat transfer test facility description /
Washington, D.C. : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2010

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Government Document Book
15
Background and derivation of ANS-5.4 standard fission product release model /
by Turnbull, J. A.
Washington, DC : U. S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2010

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Government Document Book
16
Regulatory guide 1.199 : anchoring components and structural supports in concrete.
[Washington, D.C.] : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2003

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Government Document Book
17
BWR anticipated transients without scram in the MELLLA+ expanded operating domain /
Washington, D.C. : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2015

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Government Document Book
18
Determining the Effectiveness, Limitations, and Operator Response for Very Early Warning Fire detection systems in nuclear facilities (DELORES-VEWFIRE) : draft report for comment /
by Taylor, G.
Washington, D.C. : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2015

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Government Document Book
19
Preconditioning of plant structures, systems, and components before ASME code inservice testing or technical specification surveillance testing.
[Washington, D.C.] : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 1997

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Government Document Book
20
Rod bundle heat transfer test facility test plan and design /
Washington, D.C. : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2010

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Government Document Book
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