Elevated Temperature Fatigue Characterization of Transition Joint Weld Metal and Heat Affected Zone in Support of Breeder Steam Generator Development

2009 ◽  
pp. 218-218-17 ◽  
Author(s):  
CR Brinkman ◽  
JP Strizak ◽  
JF King
2013 ◽  
Vol 446-447 ◽  
pp. 288-290
Author(s):  
Pornpibunsompop Tosapolporn

The precipitation characterization of SUS 310S weld metal was investigated by TG/DSC and metallography technique. SMAW was selected for this study and then cut with water jet avoiding thermal effect. Austenitic is the main microstructure of weld metal because of high Creqv./Nieqv. Precipitation launched higher both %mass change and heat consumed as well as the precipitation temperature was around 800 degree Celsius.


2012 ◽  
Vol 251 ◽  
pp. 252-260 ◽  
Author(s):  
J.K. Wright ◽  
L.J. Carroll ◽  
C. Cabet ◽  
T.M. Lillo ◽  
J.K. Benz ◽  
...  

2012 ◽  
Vol 18 (S2) ◽  
pp. 1668-1669
Author(s):  
B.K. Narayanan ◽  
A. Avishai
Keyword(s):  

Extended abstract of a paper presented at Microscopy and Microanalysis 2012 in Phoenix, Arizona, USA, July 29 – August 2, 2012.


Author(s):  
Mara Cardoso Gonçalves Rios ◽  
João da Cruz Payão Filho ◽  
Francisco Werley Cipriano Farias ◽  
Victor Hugo Pereira Moraes e Oliveira ◽  
Augusto Veríssimo Passos

Author(s):  
Milan Brumovsky ◽  
Milos Kytka ◽  
Petr Novosad ◽  
Jiri Brynda

Lifetime of reactor pressure vessels practically depends on a level of degradation of RPV material properties during operation. The most important degradating mechanism of RPV materials is usually radiation damage, characterized by values on neutron fluence on one side and radiation embrittlement of RPV materials on the second side. WWER reactor pressure vessels in the Czech Republic are a subject of a very thorough and complex monitoring program, that includes: • Standard material surveillance program containing of WWER-440 RPV materials — base metal, weld metal, heat affected zone, but irradiated with high lead factor (13 to 18), • Supplementary surveillance program of WWER-440 RPV materials, including additionally austenitic cladding materials, IAEA reference material JRQ irradiated with low lead factor (2 to 3) with parts subjected to annealing and re-irradiation after annealing, • Modified surveillance program of WWER-1000 RPV materials — base metal, weld metal, heat affected zone, cladding materials, IAEA reference JRQ material irradiated in low lead factor (2 to 3) near RPV inner beltline region, • Integrated surveillance specimen program for WWER-1000 reactor including materials from NPP Temelin (Czech Republic), Belene (Bulgaria), Kalinin (Russia) and Ukranian NPPs, • Continous exvessel monitoring of neutron fluence on outer RPV surface for both WWER-440 and WWER-1000 plants, • Neutron fluence determination on inner RPV surface (austenitic cladding) using special technique for removal of specimens from cladding for Nb activity measurements, • Ex-vessel temperature measurements during RPV operation. All these programs serve for precision of operation conditions and determination of degradation of RPV materials for RPV integrity and lifetime assessment.


2011 ◽  
Vol 214 ◽  
pp. 108-112 ◽  
Author(s):  
Prachya Peasura ◽  
Bovornchok Poopat

The Inconel X-750 indicates good hot corrosion resistance, high stability and strength at high temperatures and for this reason the alloy is used in manufacturing of gas turbine hot components. The objective of this research was study the effect of post weld heat treatment (PWHT) on fusion zone and heat affected zone microstructure and mechanical properties of Inconel X-750 weld. After welding, samples were solutionized at 1500 0C. Various aging temperature and times were studied. The results show that aging temperature and time during PWHT can greatly affect microstructure and hardness in fusion zone and heat affected zone. As high aging temperature was used, the grain size also increased and M23C6 at the grain boundary decreased. This can result in decreased of hardness. Moreover excessive aging temperature can result in increasing MC carbide intensity in parent phase (austenite). It can also be observed that M23C6 at the grain boundary decreased due to high aging temperature. This resulted in decreasing of hardness of weld metal and heat affected zone. Experimental results showed that the aging temperature 705 0C aging time of 24 hours provided smaller grain size, suitable size and intensity of MC carbide resulting in higher hardness both in weld metal and HAZ.


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