Effects of fuel type on the safety characteristics of a sodium-cooled fast reactor

Sumner, T.; Ghiaasiaan, S. Mostafa

doi:10.1016/j.anucene.2011.03.007

Cited by 7 publications

(2 citation statements)

References 21 publications

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“…Table 1: S-PRISM metal fuel composition by weight [6]. Initially setting the number of cycles to 400 in MCNP, the error values were considered too high for the small differences encountered in reactivity between temperatures.…”

Section: Modeling and Simulationmentioning

confidence: 99%

Preliminary neutronic study of the S-PRISM fast reactor

Moreira

2021

Braz. J. Rad. Sci.

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Waste management is a challenge currently faced by nuclear energy worldwide. Most nuclear power plants operate in a once-through cycle and all spent nuclear fuel is stored in long term. Fast reactors can recycle 96% of the material in spent nuclear fuel of thermal reactors, reducing drastically the time required to store the waste. The S-PRISM reactor is a modular, pool-type sodium-cooled fast reactor that can operate with a variety of fuel types. In this study, the advantages presented by fast reactors were briefly discussed and a preliminary analysis of the fuel pin cells was made. It was found that the isothermal coefficient of reactivity was lower than a regular PWR's, with neutron leakage playing a major role instead of coolant or doppler expansion. The k∞ showed decrease for the driver pin and increase for the blanket pin during burnup; opposite behavior was observed for the conversion ratio. No results for pin analysis were found in literature for comparison. As the simulations were carried out separately instead of in a system, the results are not representative of the whole core behavior but must be seen as a path to understand the different types of pin influence in the system.

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Section: Modeling and Simulationmentioning

confidence: 99%

Preliminary neutronic study of the S-PRISM fast reactor

Moreira

2021

Braz. J. Rad. Sci.

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“…The safety of Nuclear Power Plants (NPPs) represents one of the greatest technical challenges to human beings (Sumner & Ghiaasiaan, 2011). Alloy 690 is the most used material for steam generator (SG) tubing.…”

Section: Introductionmentioning

confidence: 99%

Corrosive Characteristics of Alloy 690 Investigated by Electrochemical Analysis

Shuai

Teng

et al. 2013

Icptt 2013

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Pitting corrosion is one of the major damage forms for Alloy 690, which is one of the usual used materials in SG tubing. It is very important to understand corrosion behavior deeply to ensure the structural integrity. In this paper, the electrochemical experiments are used to analyze the corrosion characters of Alloy 690. The results show that the corrosion rate is nearly to 0.00948 mm/a at 25 ºC, 0.01 mol·L -1 NaCl+0 mg·L -1 O 2 . The repair of the pitting is easy when the oxygen content is relatively high. Chloride ions in the solution have a certain impact on the repair potential and great influence on the pitting initiation potential. The pitting initiation potentials change from 0.64 V to 0.50 V then to 0.37 V (referring to SCE) when the content of Chloride ions increases from 0 mol/L to 0.001 mol/L to 0.01 mol/L. The competition between repair and breakdown will lead to the result of the peaks current. The repair of oxide film becomes more difficult under high potential. The difference value between pitting initiation potential and repair potential are -44.1 mV，0.0 mV，186.0 mV and 245.2 mV, respectively, when C Cl-equal to 0 mol·L -1 , 0.001 mol·L -1 , C Cl-=0.005 mol·L -1 and C Cl-=0.05 mol·L -1 . The above conclusions are important for recognizing the corrosion mechanism of Alloy 690.

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