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MARVEL team shares lessons learned through microreactor development
On June 1 at the American Nuclear Society’s Annual Conference in Denver, Colo., a team from Idaho National Laboratory presented a session titled “Lessons Learned from MARVEL Reactor Fabrication.” The presentation highlighted challenges that arose as they moved from design to manufacturing and assembly, with a focus on reactor part fabrication, Stirling engine implementation, and reactivity control system development.
Sang Woon Shin, Hee Cheon No
Nuclear Technology | Volume 73 | Number 3 | June 1986 | Pages 378-383
Technical Paper | Material | doi.org/10.13182/NT86-A16079
Articles are hosted by Taylor and Francis Online.
To investigate the denting phenomenon, the rates of corrosion occurring in simulated tube/support plate crevices were examined by using seven model boilers at 1.11 MPa. The model boilers were operated with all-volatile treatment (morpholine + hydrazine) with 15- and 100-ppm chloride concentrations constituting 10% FeCl2, 30% NaCl, and 60% CaCl2. It was found that corrosion rates increased with heat flux. A model was proposed to explain this observation, based on mechanisms that acid chloride is concentrated in the tube/support plate crevices. The model is expressed by the following equation for empty heated crevices: Good agreement was obtained by comparing the results predicted by the model with Brown’s data and the present data for empty heated crevices, and with Pathania’s data obtained at high heat flux. Based on the above equation, a model was developed to describe chloride concentration within the crevices versus heat flux for given condenser leakage rates in nuclear steam generators. Results predicted by the model show that a small increase in condenser leakage rates gives a considerable increase in chloride concentration within the crevices.