Zobrazeno 1 - 10
of 128
pro vyhledávání: '"A.G. Ware"'
Publikováno v:
Journal of Pressure Vessel Technology. 116:85-95
The Nuclear Regulatory Commission (NRC) developed Generic Safety Issue 113, “Dynamic Qualification and Testing of Large Bore Hydraulic Snubbers (LBHSs),” with the objective of evaluating the reliability of LBHS in operating commercial nuclear pow
Publikováno v:
Nuclear Engineering and Design. 133:49-62
Researchers at the Idaho National Engineering Laboratory performed an assessment of the aging of the reactor internals in boiling water reactors (BWRs), and identified the unresolved technical issues related to the degradation of these components. Th
This report presents a review of nuclear industry efforts to manage thermal fatigue, flow-accelerated corrosion, and water hammer damage to pressurized water reactor (PWR) feedwater nozzles, piping, and feedrings. The review includes an evaluation of
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a507e2c45c08961a11762a396e5d533d
https://doi.org/10.2172/464151
https://doi.org/10.2172/464151
Some motor operated valves now have higher torque switch settings due to regulatory requirements to ensure valve operability with appropriate margins at design basis conditions. Verifying operability with these settings imposes higher stem loads duri
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5080a8d4ffbc5725e198ba75b89b7be2
https://doi.org/10.2172/193916
https://doi.org/10.2172/193916
This paper discusses the results of a survey of fatigue monitoring methods developed by the nuclear industry. The paper is based on a comprehensive review of the technical literature related to the transients causing fatigue damage, the sites suscept
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9b626d06f7868aeb651b58f719c8b2f5
https://doi.org/10.2172/93884
https://doi.org/10.2172/93884
Recent test data indicate that the effects of the light water reactor (LWR) environment could significantly reduce the fatigue resistance of materials used in the reactor coolant pressure boundary components of operating nuclear power plants. Argonne
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::32abd5f536ecbd4b5a8d39f91c7bdd9b
https://doi.org/10.2172/48628
https://doi.org/10.2172/48628
Autor:
A.G. Ware
Using the methodology outlined in NUREG/CR-5603 this report evaluates (on a probabilistic basis) design rules for components in ALWRs that could be subjected to intersystem loss-of-coolant accidents (ISLOCAs). The methodology is intended for piping e
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::255d6deb482143e9fd60b95020df3067
https://doi.org/10.2172/10175393
https://doi.org/10.2172/10175393
Autor:
J.G. Arendts, A.G. Ware
Publikováno v:
Nuclear Engineering and Design. 90:271-277
Complete thermal-hydraulic and structural dynamic response analysis of piping systems subjected to a thermal hydrodynamic transient, such as a safety/relief valve (S/RV) opening, is a complex multi-step process. The four links of this analysis chain
Autor:
J.G. Arendts, A.G. Ware
Publikováno v:
Nuclear Engineering and Design. 89:19-25
A program has been conducted at the Idaho National Engineering Laboratory to study structural damping data for nuclear piping systems and to evaluate if changes in allowable damping values for structural seismic analyses are justified. The existing p