RAQUEL DE MORAES LOBO

RAQUEL DE MORAES LOBO

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Small punch tests with a recently developed device in IPEN
2021 - MIRANDA, C.A.J.; ANDRADE, A.H.P. de; CASTAGNET, M.; LOBO, R.M.; FALOPPA, A.A.; MATTAR NETO, M.; LIMA, J.R.; PEREIRA, L.S.
Small punch test devices in development at IPEN aiming to perform tests in RMB hot cells
2021 - MIRANDA, C.A.J.; LIMA, J.R.; FALOPPA, A.A.; ANDRADE, A.H.P. de; MATTAR NETO, M.; CASTAGNET, M.; LOBO, R.M.; PEREIRA, L.S.
Numerical analysis of the small punch test for different theoretical materials
2021 - PEREIRA, L.S.; MATTAR NETO, M.; MIRANDA, C.A.J.; LIMA, J.R.; FALOPPA, A.A.; ANDRADE, A.H.P. de; CASTAGNET, M.; LOBO, R.M.
Advances in the understanding of the mechanisms of iodine-induced SCC cracking in zirconium alloys
2019 - LOBO, RAQUEL de M.; ANDRADE, ARNALDO H.P. de
In pressurized water reactors (PWR) the fuel rod cladding is the first barrier against the spread of fission products. It is therefore essential to guarantee its use in the reactor. Sometimes the production of electricity requires that certain power plants operate in “network monitoring”. The fuel introduced into nuclear power reactors can then undergo so metimes significant power variations. Following a severe reactor power transient, clad failure can occur through a stress corrosion phenomenon (SCC), under the combined action of mechanical stresses and gaseous fission products generated by the fuel pellets. Among those iodine plays a major role, for it may induce SCC in zircaloy. In the early ages of water cooled reactors (PWRs, BWRs or CANDU), series of similar failures took place following sharp startups. Today power increase rates as well as instantaneous local power levels are limited. Indeed, it is well know that cladding failure by iodine induced stress corrosion cracking (I SCC) may occur under pellet cladding interactions (PCI) conditions during power transients in PWRs. In this paper we review the advances in the understanding of these SCC cracking mechanisms of the fuel rod cladding that would then allow better control of the integrity of the clad during the more severe demands related to the operating conditions of th e PWRs.
Monitoring of the ductile to brittle transition temperature of reactor pressure vessel steels by means of small specimens
2019 - ANDRADE, ARNALDO H.P. de; MIRANDA, CARLOS A.J.; LOBO, RAQUEL de M.
Neutron irradiation in nuclear power plants (NPPs) lead to microstructural changes in structural materials which induce a shift of the ductile to brittle transition temperature (DBTT) towards higher temperatures. Monitoring of the DBTT in NPP components receives therefore considerable attention. Small specimen testing techniques are developed for characterizing structural components with a limited amount of materials. One of the most used of these miniature testing is the small punch test (SPT) which is based on disc or square shaped specimens. SPTs may be performed from room to cryogenic temperatures, plotting the absorbed energy until rupture, against the test temperature. A ductile region (high energy) and a brittle region (low energy) with a transition between both zones are usually reported. The transition temperature thus obtained, DBTTSPT, is also related through empirical expressions to the transition temperature obtained in CVN tests, DBTTCVN, or in fracture toughness testing. Linear expressions such as DBTTSPT = α DBTTCVN have been used where α is a material characteristic constant. In all cases, the DBTTSPT temperature is much lower than that obtained in the CVN tests. In this paper, we present a short review of the literature on the determination of the DBTT for nuclear reactors pressure vessels steels by those two techniques analyzing the reason for the difference in their value as mentioned before. In dealing with irradiated materials, is a high priority to limit the exposure of the professional to irradiation. Therefore, the use of miniature specimens receives significant attention in the nuclear community. The high cost of irradiation experiments is a further incentive for using small specimen testing techniques.
Small specimen technique for assessing the mechanical properties of metallic components
2017 - LOBO, RAQUEL M.; ANDRADE, ARNALDO H.P.; MORCELLI, APARECIDO E.
Recent advances on charpy specimen reconstitution techniques
2017 - ANDRADE, ARNALDO H.P.; LOBO, RAQUEL M.; MIRANDA, CARLOS A.J.
Charpy specimen reconstitution is widely used around the world as a tool to enhance or supplement surveillance programs of nuclear reactor pressure vessels. The reconstitution technique consists in the incorporation of a small piece from a previously tested specimen into a compound specimen, allowing to increase the number of tests. This is especially important if the available materials is restricted and fracture mechanics parameter have to be determined. The reconstitution technique must fulfill some demands, among them tests results like the original standard specimens and the loaded material of the insert must not be influenced by the welding and machining procedure. It is known that reconstitution of Charpy specimens may affect the impact energy in a consequence of the constraint of plastic deformation by the hardened weldment and HAZ. This paper reviews some recent advances of the reconstitution technique and its applications.
Novas ligas de zirconio para apliccao nuclear
2010 - LOBO, R.M.; ANDRADE, A.H.P.
Obtencao experimental de acetato de praseodimio de alta pureza a partir de carbonatos mistos de terras raras
2010 - QUEIROZ, C.A. da S.; ROCHA, S.M.R. da; PEDREIRA, W.R.; SENEDA, J.A.; LOBO, R.M.; FILHO, W.S.
Effect of coupon orientation on corrosion behavior of aluminium alloy coupons in the spent fuel storage section of the IEA-R1 research reactor
2004 - CORREA, O.V.; LOBO, R.M.; FERNANDES, S.M.C.; MARCONDES, G.; RAMANATHAN, L.V.