scholarly journals Influence of the transient conditions on release of corrosion products and oxidation of alloy 690 tubes during pressurized water reactor restart after steam generators replacement

2021 ◽  
Vol 543 ◽  
pp. 152562
Author(s):  
Julie Flambard ◽  
Florence Carrette ◽  
Carole Monchy-Leroy ◽  
Eric Andrieu ◽  
Lydia Laffont
Keyword(s):  
Corrosion Products ◽  
Pressurized Water Reactor ◽  
Steam Generators ◽  
Pressurized Water ◽  
Transient Conditions ◽  
Water Reactor ◽  
Alloy 690

The response of alloy 690 tubing in a pressurized water reactor environment

2007 ◽  
Vol 28 (2) ◽  
pp. 373-379 ◽  
Author(s):  
B.A. Young ◽  
Xiaosheng Gao ◽  
T.S. Srivatsan ◽  
Peter J. King
Keyword(s):  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Water Reactor ◽  
Alloy 690

Corrosion Mechanisms of Ni-Base Alloys in Pressurized Water Reactor Primary Conditions

2008 ◽  
Vol 595-598 ◽  
pp. 529-537 ◽  
Author(s):  
Loïc Marchetti ◽  
Stéphane Perrin ◽  
Olivier Raquet ◽  
Michèle Pijolat
Keyword(s):  
Film Formation ◽  
Oxidation Mechanism ◽  
Passive Layer ◽  
Pressurized Water Reactor ◽  
Primary Coolant ◽  
Pressurized Water ◽  
Water Reactor ◽  
Boundary Diffusion Coefficient ◽  
Alloy 690 ◽  
Corrosion Mechanisms

Oxidation mechanism of Alloy 690 has been investigated in Pressurised Water Reactor (PWR) primary coolant conditions (325°C, aqueous hydrogenated media). Experiments performed with gold marker and RBS technique reveal that the passive film formation is the consequence of an anionic mechanism. This result is confirmed by experiments achieved with two sequences of corrosion in a H2 16O media and in a mixed H2 16O/ H2 18O media. The localisation of 18O by SIMS analysis in the thin passive layer underlines an oxidation mechanism due to oxygen diffusion by short circuits (like grain boundaries) in the oxide scale. Moreover grain boundary diffusion coefficient in chromite like oxide was estimated to be in the range 2 10-18 – 1 10-17 cm2.s-1 and compared to values extrapolated from higher temperature.

Analysis of PRHRS for an Integral Pressurized Water Reactor Using RELAP5/MOD3.4

2010 ◽  
Author(s):  
Xuhua Ye ◽  
Minjun Peng ◽  
Jiange Liu
Keyword(s):  
Natural Circulation ◽  
Heat Removal ◽  
Parameter Study ◽  
Pressurized Water Reactor ◽  
Steam Generators ◽  
Primary Coolant ◽  
Pressurized Water ◽  
Water Reactor ◽  
Pressure Peak ◽  
Residual Heat

An investigation on the thermal hydraulic characteristics of the passive residual heat removal system (PRHRS) which is used in an integral pressurized water reactor (INSURE-100) is presented in this paper. The main components of primary coolant system are enclosed in reactor vessel. Primary fluid flow circle is natural circulation. The PRHRS can remove the energy from the primary side as long as the residual heat exchanger (RHE) is submerged in the emergency cooldown tank (ECT). The parameter study is performed by considering the effects of an effective height between the steam generators and the RHE and a valve actuation time, which are useful for the design of the PRHRS. The mass flow in the PRHRS has been affected by the height difference between the steam generators and the RHE. The pressure peak of the primary side and PRHRS has been affected by the valve action time.

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