Inherent safety aspects of metal fuelled FBR

Sathiyasheela, T.; Riyas, A.; Sukanya, R.; Mohanakrishnan, P.; Chetal, S.C.

doi:10.1016/j.nucengdes.2013.02.050

Cited by 6 publications

(2 citation statements)

References 16 publications

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“…This assumption has been used by ANL [28] (US), Brookhaven National Laboratory (BNL) [29] (US), Massachusetts Institute of Technology (MIT) [30] (US), Korea Atomic Energy Research Institute (KAERI) [31] (Korea), Indira Gandhi Centre for Atomic Research (IGCAR) [32] (India) and many others. It appears to be an un-physical simplification for standard metallic fuel, since Y f is certainly larger than 0 Pa. More importantly, in some accident scenarios, this assumption leads to non-conservative results.…”

Section: Methods and Definitionsmentioning

confidence: 99%

Optimizing the Design of Small Fast Spectrum Battery-Type Nuclear Reactors

Qvist

2014

Energies

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This study is focused on defining and optimizing the design parameters of inherently safe "battery" type sodium-cooled metallic-fueled nuclear reactor cores that operate on a single stationary fuel loading at full power for 30 years. A total of 29 core designs were developed with varying power and flow conditions, including detailed thermal-hydraulic, structural-mechanical and neutronic analysis. Given set constraints for irradiation damage, primary cycle pressure drop and inherent safety considerations, the attainable power range and performance characteristics of the systems are defined. The optimum power level for a core with a coolant pressure drop limit of 100 kPa and an irradiation damage limit of 200 DPA (displacements per atom) is found to be 100 MWt/40 MWe. Raising the power level of an optimized core gives significantly higher attainable power densities and burnup, but severely decreases safety margins and increases the irradiation damage. A fully optimized inherently safe battery-type fast reactor core with an active height and diameter of 150 cm (2.6 m 3 ), a pressure drop limit of 100 kPa and an irradiation damage limit of 300 DPA can be designed to operate at 150 MWt/60 MWe for 30 years, reaching an average discharge burnup of 100 MWd/kg-actinide.

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Section: Methods and Definitionsmentioning

confidence: 99%

Optimizing the Design of Small Fast Spectrum Battery-Type Nuclear Reactors

Qvist

2014

Energies

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“…The thermal expansion coefficient is one of the important properties in fuel pin design and performance modeling. For instance, an increase in fuel volume and associated decrease in density due to thermal expansion can cause enhanced neutron leakage and hence negative feedback [70]. Therefore, it is important to understand the influence of point defects on the thermal expansion coefficient.…”

Section: Systemmentioning

confidence: 99%