Comparative study on nuclear characteristics of APR1400 between 100% MOX core and UO2 core

Salam, Mahrus; Hah, Chang Joo

doi:10.1016/j.anucene.2018.05.008

Cited by 9 publications

(2 citation statements)

References 3 publications

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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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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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“…Korean Utility Requirements (KUR) states that the design of nuclear reactors with MOX fuel can reach 30% of the core. At present, EUR (European Utility Requirements) has a nuclear design capability of up to 50% MOX in its core [5] and APR1400 has successfully demonstrated the ability to design a core with 50% MOX on it to obtain EUR certification [7].…”

Section: Introduction *mentioning

confidence: 99%

Calculation of 2-Dimensional PWR Mox/Uo2 Core Benchmark Oecd Nea 6048 With Srac Code

Luthfi

Pinem

2020

Tri Dasa Mega

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The mixed uranium-plutonium oxide fuel (MOX/UO2) is an interesting fuel for future power reactors. This is due to the large amount of plutonium that can be processed from spent fuel of nuclear plants or from plutonium weapons. MOX/UO2 fuel is very flexible to be applied in thermal reactors such as PWR and it is more economical than UO2 fuel. However, due to the different nature of neutron interactions of MOX in PWR, it will change the reactor core design parameters and also its safety characteristic. The purpose of this study is to determine the accuracy of SRAC2006 code system in generation of cross-sections and calculation of reactor core design parameters such as criticality, reactivity of control rods and radial power distribution. In this study, PWR MOX/UO2 Core Transient Benchmark is used to verify the code that models a MOX/UO2 fueled core. SRAC-CITATION result is different from DeCART by 0.339% from. SRAC-CITATION result of single rod worth in All Rods Out (ARO) conditions are quite good with a maximum difference of 6.34% compared to BARS code and 4.74% compared to PARCS code. In All Rods In (ARI) condition, SRAC-CITATION results compared to the PARCS code is quite good where the maximum difference is 9.72%, but compared to BARS code, it spikes up to 33.24% at maximum difference. In the other case, overall radial power density results are quite good compared to the reference. Its maximum deviation from DeCART code is 5.325% in ARO condition and 6.234% in ARI condition. Based on the results of these calculations, SRAC code system can be used to generate cross-section and to calculate some neutronic parameters. Hence, it can be used to evaluate the neutronic parameters of the MOX/UO2 PWR core design.Keywords: MOX/UO2 fuel, Criticality, Power peaking factor, SRAC2006

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Whole-core analyses on recriticality of conventional high power pressurized water reactor in Korea during early phase of severe accidents

Lee

Cho

Lim

2020

Annals of Nuclear Energy

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Comparative study on nuclear characteristics of APR1400 between 100% MOX core and UO2 core

Cited by 9 publications

References 3 publications

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

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

Calculation of 2-Dimensional PWR Mox/Uo2 Core Benchmark Oecd Nea 6048 With Srac Code

Whole-core analyses on recriticality of conventional high power pressurized water reactor in Korea during early phase of severe accidents

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