Preliminary design study of a board type radial fuel shuffling sodium cooled breed and burn reactor core

Zheng, Meiyin; Tian, Wenxi; Xiao, Changfu; Zhang, Dalin; Qiu, Suizheng; Su, G.H.

doi:10.1016/j.nucengdes.2014.08.017

Cited by 5 publications

(2 citation statements)

References 16 publications

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“…The first SWR core design was conducted at Brookhaven National Laboratory (BNL) in collaboration with the Massachusetts Institute of Technology (MIT) in 1970s. After that, the studies of SWR were performed by Marshall et al (2005), Greenspan and Heidet (2009), Chen et al (2011), Greenspan (2012, 2013), Qvist and Greenspan (2012), Zhang et al (2013), Zheng et al (2014aZheng et al ( , 2014bZheng et al ( , 2015, and so on. In 2008, the Terra Power LLC was founded to develop commercial TWR (actually SWR), which brings a huge boost to the investigation of Breed and Burn reactors.…”

Section: Introductionmentioning

confidence: 99%

Performance of radial fuel shuffling sodium cooled Breed and Burn reactor core

Zheng

Tian

Zhang

et al. 2016

Annals of Nuclear Energy

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a b s t r a c tIn this paper, performance of radial fuel shuffling of sodium cooled Breed and Burn reactor core is investigated. Neutronics and depletion calculations are carried out by MCORE based on the ENDF/B-VII data library. Thermal-hydraulic analysis is performed based on a self-developed parallel channels model steady-state code SAST. First of all, the assembly parameters are optimized from neutronics and thermal-hydraulics. The results show that assembly with 127 fuel rods and P/D of 1.12 is the best design. Secondly, the core critical features and radial power peaking factors of the inward and outward fuel shuffling strategy under different fuel shuffling periods are carried out. The results show that k eff of the beginning of equilibrium cycle (BOEC) and end of equilibrium cycle (EOEC) of both the inward and outward fuel shuffling strategy parabolically vary with the fuel shuffling period. Power peaking factor of the inward fuel shuffling strategy decreases with the increase of fuel shuffling period exponentially, while that of the outward fuel shuffling strategy increases with the fuel shuffling period exponentially. The outward fuel shuffling strategy with shuffling period of 500 days performs better in core critical features and radial power peaking factors. Reactivity coefficients of the optimized core are calculated. Finally, preliminary thermal-hydraulic analysis of the optimized core is performed. The results show that maximum cladding interface temperature and maximum fuel temperature are all within the acceptable limits.

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Section: Introductionmentioning

confidence: 99%

Performance of radial fuel shuffling sodium cooled Breed and Burn reactor core

Zheng

Tian

Zhang

et al. 2016

Annals of Nuclear Energy

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“…Most probably inspired by our idea of continuous radial fuel shuffling, Seifritz [19] obtained an analytic solution for the outward fuel shuffling, as he assumed that the nonlinear term in his fluence equation is a sine function of fluence. It is worth mentioning here that there are a lot of TWR research activities carried out world widely and readers are referred, e.g., to [20][21][22][23][24] and their references.…”

Section: Introductionmentioning

confidence: 99%

Asymptotic Solutions of Serial Radial Fuel Shuffling

Chen

Kiefhaber

2015

Energies

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Abstract:In this paper, the mechanism of traveling wave reactors (TWRs) is investigated from the mathematical physics point of view, in which a stationary fission wave is formed by radial fuel drifting. A two dimensional cylindrically symmetric core is considered and the fuel is assumed to drift radially according to a continuous fuel shuffling scheme. A one-group diffusion equation with burn-up dependent macroscopic coefficients is set up. The burn-up dependent macroscopic coefficients were assumed to be known as functions of neutron fluence. By introducing the effective multiplication factor keff, a nonlinear eigenvalue problem is formulated. The 1-D stationary cylindrical coordinate problem can be solved successively by analytical and numerical integrations for associated eigenvalues keff. Two representative 1-D examples are shown for inward and outward fuel drifting motions, respectively. The inward fuel drifting has a higher keff than the outward one. The 2-D eigenvalue problem has to be solved by a more complicated method, namely a pseudo time stepping iteration scheme. Its 2-D asymptotic solutions are obtained together with certain eigenvalues keff for several fuel inward drifting speeds. Distributions of the neutron flux, the neutron fluence, the infinity multiplication factor kinf and the normalized power are presented for two different drifting speeds.

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Introduction to Breed and Burn Reactors

Qvist¹

2021

Encyclopedia of Nuclear Energy

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Preliminary design study of a board type radial fuel shuffling sodium cooled breed and burn reactor core

Cited by 5 publications

References 16 publications

Performance of radial fuel shuffling sodium cooled Breed and Burn reactor core

Performance of radial fuel shuffling sodium cooled Breed and Burn reactor core

Asymptotic Solutions of Serial Radial Fuel Shuffling

Introduction to Breed and Burn Reactors

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