Analysis of actinide recycling in a Boiling Water Reactor using CASMO-4/SIMULATE-3

Ramírez, José Ramón; Alonso, Gustavo; Martinez, Eduardo; Castillo, Rogelio; Palacios, Javier

doi:10.1016/j.pnucene.2016.02.003

Cited by 9 publications

(4 citation statements)

References 7 publications

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“…Good agreement was found between the 2D and 3D Serpent models, though the 2D 1FA model slightly overestimated keff at beginning of cycle (BOC) as it was modelled as being axially infinite, whereas the 3D 4FA modelled a fuel bundle with a fixed height. Nevertheless, the discrepancies between models were deemed to be acceptable and found to be within generally accepted tolerances (Ramirez, et al, 2016) (O'Donnell, et al, 2001). The 3D model was used for the purposes of calculation since results of previous studies have suggested that 2D models may underestimate certain parameters, for example, the achievable burnup.…”

Section: Methods 21 Pu Vectors and Model Set-upmentioning

confidence: 99%

“…Results showed that, with axial zoning, up to 90% of the loaded Am could be incinerated for burnups of 60-80 GWd/tHM, and optimisation of the Am location within the fuel bundles improved transmutation by ~3% by the end of the first cycle. (Ramirez, et al, 2016) considered radial-only zoning of MAs in a full core such that 4 pins in each assembly contained ~6%wt MAs with U enrichment varied to achieve the same kinf behavior as the UO2 reference case. Axial zoning was accounted for, but this only applied to UO2 enrichment, while MA content remained constant.…”

Section: Effect Of Am On Performancementioning

confidence: 99%

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The effect of Am241 on UK plutonium recycle options in thorium-plutonium fuelled LWRs – Part II: BWRs

Morrison

Parks

2020

Annals of Nuclear Energy

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UK plutonium is expected to be managed using uranium-plutonium (U-Pu) mixed oxide (MOX) fuels in Light Water Reactors (LWRs). However, studies have shown that thorium-plutonium (Th-Pu) may be preferential. Part I of this study considered the effect of americium (Am) in UK Pu in Pressurized Water Reactors (PWRs) and found that, while the reactivity response was sensitive to isotopic and spectral variations, trends were predictable. Part II focusses on separation of Am in Boiling Water Reactors (BWRs) and compares fuel performance to the uniformly distributed and spatially separated cases outlined in Part I. Comparable incineration rates are achievable but, while a single PWR assembly bears a greater mass of Am/Pu than a single BWR assembly, the full BWR core may be capable of operating with significantly greater fissile masses. Transmutation of Am241 to Am242 appears preferable to fast fission of Am241 as increased incineration occurs in lower void, bottom-of-assembly locations.

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Section: Methods 21 Pu Vectors and Model Set-upmentioning

confidence: 99%

Section: Effect Of Am On Performancementioning

confidence: 99%

The effect of Am241 on UK plutonium recycle options in thorium-plutonium fuelled LWRs – Part II: BWRs

Morrison

Parks

2020

Annals of Nuclear Energy

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“…While standard U-Pu MOX options have been considered (Gul, et al, 2018) (Salam & Hah, 2018) (Alonso, et al, 2018) (Ramirez, et al, 2016) (Haas & Hamilton, 2007) (Cowell & Fisher, 1999) (Schlosser, et al, 1993), studies have shown that Th-Pu MOX may provide a promising alternative (Ernoult, et al, 2015) (Lau, et al, 2014) (Revol, et al, 2013) (National Nuclear Laboratory, 2012 (Fridman & Kliem, 2011) (International Atomic Energy Agency, 2005) (International Atomic Energy Agency, 2002) (Galperin, 1995) (Cadelli & Lippens, 1988) (Shapiro, et al, 1977). The high conversion ratio and lack of breeding of additional Pu in the Th-cycle results in significantly lower Pu / MA content in discharged fuel compared to standard U-Pu MOX, leading to potentially lower levels of radiotoxicity and decay heat of associated waste materials compared to standard UO2 and U-Pu fuels (Hesketh & Thomas, 2013) (International Atomic Energy Agency, 2005).…”

Section: Viable Technologies For Pu Dispositionmentioning

confidence: 99%

The effect of Am241 on UK plutonium recycle options in thorium-plutonium fuelled LWRs – Part I: PWRs

Morrison

Parks

2020

Annals of Nuclear Energy

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UK plutonium is expected to be managed using uranium-plutonium (U-Pu) mixed oxide (MOX) fuels in Light Water Reactors (LWRs). However, studies have shown that thorium-plutonium (Th-Pu) may be preferential. Research has mostly focussed on recycle of reactor grade Pu with limited minor actinide (MA) content. This study will determine if large quantities of americium (Am) in UK Pu may be restrictive to recycle schemes by determining the effect this has on reactivity feedback coefficients, fissile loading and incineration potential. Addition of Am is shown to result in predictable trends in reactivity feedback coefficients and spatial separation of Am and Pu is found to offer potential advantages over uniformly loaded fuel in terms of maximising fissile loading and incineration. Separation may also offer benefits in terms of targeting Am destruction, particularly if multiple recycle schemes are pursued, as this would maximise the fissile loading requirements while keeping reactivity feedback coefficients negative.

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“…The numbers inside are Pu concentration, without actinides load The next fuel cell was made replacing 4 rods of MOX fuel containing 5.73% of plutonium per 4 rods containing 6% of actinides with the previously specified vector in a depleted uranium matrix [6] (Figure 8).…”

Section: The Numbers Inside Boxes Represent Pu Concentrationmentioning

confidence: 99%

MOX Fuel Alternatives for Minor Actinides Burnup in Thermal Spectrum

SJR¹

2019

Journal of Waste Resources and Recycling

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The strategy used in this work was the following; first, it was necessary to establish the material of study for the actinides generation. This material was the commercial uranium oxide fuel and take it as a reference, then to design a MOX fuel cell. Starting with the uranium oxide fuel, this MOX design was made scaling the radial uranium enrichments to plutonium concentrations making use of a Fissile Material Ratio (FMR) which was found in previous work as the equivalent in a MOX fuel cycle. It is a relation between the uranium enrichments to concentrations of reactor grade plutonium, to obtain the MOX fuel cell [2]. In the MOX fuel cell, the gadolinium rods remains without changes as in the case of the UOX fuel assembly, with all this made we get a reference for the UOX and MOX fuel cells.Taken the first MOX fuel cell as model, we replace eight fuel rods by water rods to increase the moderator to fuel ratio and determine the actinides production, the results obtained are shown in section 6.A flow diagram of the calculations made in this paper is shown in Figure 1.

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Analysis of actinide recycling in a Boiling Water Reactor using CASMO-4/SIMULATE-3

Cited by 9 publications

References 7 publications

The effect of Am241 on UK plutonium recycle options in thorium-plutonium fuelled LWRs – Part II: BWRs

The effect of Am241 on UK plutonium recycle options in thorium-plutonium fuelled LWRs – Part II: BWRs

The effect of Am241 on UK plutonium recycle options in thorium-plutonium fuelled LWRs – Part I: PWRs

MOX Fuel Alternatives for Minor Actinides Burnup in Thermal Spectrum

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