Analysis of core life-time and neutronic parameters for HEU and potential LEU/MEU fuels in a typical MNSR

Nawaz, Amjad; Mirza, Sikander M.; Mirza, Nasir M.; Sohail, Muhammad

doi:10.1016/j.anucene.2012.04.005

Cited by 8 publications

(2 citation statements)

References 14 publications

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“…Attributes of aluminum and its alloys include light weight, high strength and excellent corrosion resistance, which have led to widespread applications 1 . In the nuclear field, aluminum is a component of fuel (UO 2 /Al, U-Si/Al, U-Mo/Al, and U-Al/Al) and fuel cladding 2 , and is also among the most promising metallic solvents and electrode materials for actinide-lanthanide pyroprocessing separations 3 . However, handling the resulting radioactive aluminum alloys by aqueous reprocessing can be challenging as its use of strong acids for dissolution may be complex and will generate abundant radioactive liquid waste 3 , while by chlorination route use of reactive gases like Cl 2 or HCl for high-temperature chlorination will corrode equipment and present additional hazards 4 .…”

Section: Introductionmentioning

confidence: 99%

In-situ anodic precipitation process for highly efficient separation of aluminum alloys

Zhong

Liu

et al. 2021

Nat Commun

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Electrorefining process has been widely used to separate and purify metals, but it is limited by deposition potential of the metal itself. Here we report in-situ anodic precipitation (IAP), a modified electrorefining process, to purify aluminium from contaminants that are more reactive. During IAP, the target metals that are more cathodic than aluminium are oxidized at the anode and forced to precipitate out in a low oxidation state. This strategy is fundamentally based on different solubilities of target metal chlorides in the NaAlCl4 molten salt rather than deposition potential of metals. The results suggest that IAP is able to efficiently and simply separate components of aluminum alloys with fast kinetics and high recovery yields, and it is also a valuable synthetic approach for metal chlorides in low oxidation states.

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Section: Introductionmentioning

confidence: 99%

In-situ anodic precipitation process for highly efficient separation of aluminum alloys

Zhong

Liu

et al. 2021

Nat Commun

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“…everal Low Enriched Uranium Fuels are available for research reactors core conversion studies from High Enriched Uranium (HEU) to Low Enriched Uranium (LEU) Fuel (Matos and Lell, 2005, IAEA, 1992, Nawaz et al, 2012. The majority of research conducted on this type of studies for the Nigeria Research Reactor (NIRR-1) focused on the use of Low Enriched Uranium dioxide (UO2) fuel with Zirconium alloy cladding.…”

Section: Introductionmentioning

confidence: 99%

Investigating Possibilities of fuelling NIRR-1 with Low Enriched Uranium Silicide-Aluminum Dispersion Fuels

et al. 2021

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In the last quarter of 2018, low enriched uranium dioxide fuel with zirconium alloy cladding was used successfully to convert the core of NIRR-1 from HEU to LEU fuel and the removed core returned to the country of origin. The objective of this study was to investigate the possibility of fueling the same system with alternate LEU fuel for future replacement of the current fuel, without any unacceptable compromise in reactor performance. Having more than one fuel options available for the same reactor system will present Nigeria an opportunity of making good economic decisions at the end of the cycle of the current LEU fuel. The performance of low enriched uranium silicide aluminum dispersion fuels in the core of NIRR-1 has been investigated and the results were identical with that of similar studies conducted elsewhere for generic MNSR system. Some of the calculated reactor parameters using this alternate LEU fuel were closely identical with that of the old HEU core. The computer software selected for this studies were the SCALE code system and the VENTURE PC. While the SCALE code system was employed to generate a properly averaged multigroup cross section library for the investigated LEU core models for NIRR-1 system, the VENTURE PC was utilized to give criticality information, few group fluxes and power density distributions within the core of the modeled system.Keywords— Reactor, Reactivity, Fuel, Enriched, Silicide

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Neutronic assessment of BDBA scenario at the end of Isfahan MNSR core life

Ahmadi

Pirouzmand

Rabiee

2018

Nuclear Engineering and Technology

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Analysis of core life-time and neutronic parameters for HEU and potential LEU/MEU fuels in a typical MNSR

Cited by 8 publications

References 14 publications

In-situ anodic precipitation process for highly efficient separation of aluminum alloys

In-situ anodic precipitation process for highly efficient separation of aluminum alloys

Investigating Possibilities of fuelling NIRR-1 with Low Enriched Uranium Silicide-Aluminum Dispersion Fuels

Neutronic assessment of BDBA scenario at the end of Isfahan MNSR core life

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