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Keywords: PWR
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Proceedings Papers

Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A001, July 13–15, 2021
Paper No: PVP2021-61728
... was revised slightly to make it consistent with the n slope of the log(da/dN) versus log( K) curve (i.e., regression analysis of the original data. exponent on K), dimensionless Keywords: fatigue crack growth, reference curves, PWR, fatigue threshold, R-ratio effects. R Kmin/Kmax = R-ratio, dimensionless...
Proceedings Papers

Proc. ASME. PVP2021, Volume 3: Fluid Structure Interaction; High Pressure Technology, V003T04A014, July 13–15, 2021
Paper No: PVP2021-65000
... pressure would increase significantly across the baffle plates. PWRs include safety features such as Loss-of-Coolant-Accident (LOCA) holes and slots in the core periphery baffles surrounding the fuel assemblies to release the pressure build up during a LOCA event. Accordingly, these fuel assemblies...
Proceedings Papers

Proc. ASME. PVP2021, Volume 4: Materials and Fabrication, V004T06A038, July 13–15, 2021
Paper No: PVP2021-62368
... Proceedings of the ASME 2021 Pressure Vessels & Piping Conference PVP2021 July 13-15, 2021, Virtual, Online PVP2021-62368 APPLICATION OF LEAK-BEFORE-BREAK TO SMALL DIAMETER STAINLESS STEEL PIPING IN PWRS Nathaniel G. Cofie, Dilip Dedhia, Do Jun Shim Structural Integrity Associates, Inc. San Jose...
Proceedings Papers

Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A001, August 3, 2020
Paper No: PVP2020-21051
...APPLICATION OF NICKEL ELECTROPLATING FOR PWR REACTOR PRESSURE VESSEL CLADDING REPAIR Seong Sik Hwang1, Dong Jin Kim1 1 Korea Atomic Energy Research Institute, 989-111 Daedeok-daero,Yuseong, Daejeon, Korea, 34057 ABSTRACT SA508 low-alloy steel for a reactor vessel was exposed to primary water...
Proceedings Papers

Proc. ASME. PVP2019, Volume 1: Codes and Standards, V001T01A021, July 14–19, 2019
Paper No: PVP2019-93855
...-royce.com ABSTRACT The reference Fatigue Crack Growth (FCG) rate behaviour for austenitic stainless steel in a deaerated Pressurised Water Reactor (PWR) environment is provided in ASME Section XI Code Case N-809. This FCG law is dependent on load ratio and environmental factors in terms of a defined...
Proceedings Papers

Proc. ASME. PVP2019, Volume 3: Design and Analysis, V003T03A027, July 14–19, 2019
Paper No: PVP2019-93282
... and extent of the vibrations. Demonstration of acceptable vibration levels in the ADS system was a key engineering accomplishment for AP1000® fuel load. Keywords: vibration, piping, PWR, AP1000 Nomenclature ADS Automatic Depressurization System ADS-123 ADS Stage 1, 2, and 3 ADS-4 ADS Stage 4 BWR Boiling...
Proceedings Papers

Proc. ASME. PVP2013, Volume 6B: Materials and Fabrication, V06BT06A062, July 14–18, 2013
Paper No: PVP2013-97238
... in nuclear power plants has to be assessed to meet given safety criteria. For a better understanding of the in-service loads in welded areas of PWRs components, the residual stresses resulting from the welding process have to be estimated. For that purpose, numerical simulations of welding have proved...
Proceedings Papers

Proc. ASME. PVP2013, Volume 3: Design and Analysis, V003T03A039, July 14–18, 2013
Paper No: PVP2013-97510
... Water Reactor (PWR) has to be assessed to meet safety criteria. This paper deals with crack-propagation under cyclic thermo-mechanical loadings, as encountered in class I austenitic pipes of PWR s. To have a conservative and reliable assessment of the crack propagation due to the in-service loading...
Proceedings Papers

Proc. ASME. PVP2009, Volume 3: Design and Analysis, 263-272, July 26–30, 2009
Paper No: PVP2009-77156
... In order to estimate the crack initiation damage, and also the water leakage conditions on PWR pipes, uniaxial fatigue curves are often used. They were deduced from strain or stress load control tests using normalised cylindrical specimens. However, severe thermo-mechanical loading fluctuations...
Proceedings Papers

Proc. ASME. PVP2007, Volume 1: Codes and Standards, 287-302, July 22–26, 2007
Paper No: PVP2007-26755
... of the applied stress intensity factor range (ΔK). No reference curves for water-wetted defects in austenitic stainless steels are currently available. This paper describes the results of testing of austenitic stainless steel and weld metal in simulated PWR primary coolant over a range of temperatures...
Proceedings Papers

Proc. ASME. PVP2005, Volume 1: Codes and Standards, 193-205, July 17–21, 2005
Paper No: PVP2005-71563
... ) as a function of the applied stress intensity factor range (ΔK). No reference curves for water-wetted defects in austenitic stainless steels are currently available. This paper describes the results of testing of Type 304L stainless steel in simulated PWR primary coolant over a range of temperatures...
Proceedings Papers

Proc. ASME. PVP2006-ICPVT-11, Volume 3: Design and Analysis, 535-544, July 23–27, 2006
Paper No: PVP2006-ICPVT-11-93658
... is the most damaging case. Such difference is not due to difference on microscopic mechanisms for that temperature range. It results from a pure mechanical origin: a biaxial state corresponds to an increase of the hydrostatic stress. PWR thermal fatigue biaxial effect crack initiation Proceedings...