“CANDLE” burnup regime after LWR regime

Sekimoto, Hiroshi; Nagata, Akito

doi:10.1016/j.pnucene.2007.10.012

Cited by 9 publications

(2 citation statements)

References 5 publications

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“…CANDLE (stands for Constant Axial shape of Neutron flux, nuclide densities, and power shape During Life of Energy production) burnup strategy since published in 2000/2001 [3], has been extensively studied by many researchers in Japan and other countries [4][5][6][7][8][9][10][11].…”

Section: Introductionmentioning

confidence: 99%

Application of Modified CANDLE Burnup to Very Small Long Life Gas-Cooled Fast Reactor

Monado

Su’ud

Waris

et al. 2013

AMR

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Section: Introductionmentioning

confidence: 99%

Application of Modified CANDLE Burnup to Very Small Long Life Gas-Cooled Fast Reactor

Monado

Su’ud

Waris

et al. 2013

AMR

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“…Breedand-burn reactors are also known as traveling wave reactors and convert-and-burn reactors. Past examples of breed-and-burn reactor concepts and analysis are given in references [1] through [4].…”

Section: Introductionmentioning

confidence: 99%

Using the Neutron Excess Concept to Determine Starting Fuel Requirements for Minimum Burnup Breed-and-Burn Reactors

2011

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In a breed-and-burn (B&B) reactor, the reactor is first started with enriched uranium or other fissile material, but can be thereafter refueled with natural or depleted uranium. B&B reactors have the potential to achieve >10% uranium utilization in a once-through fuel cycle, versus <1% for LWRs. A newly developed method for analyzing B&B reactors-the "neutron excess" conceptis used to determine the minimum amount of startup fuel needed to establish a desired equilibrium cycle in a minimum-burnup B&B reactor. Here a minimum-burnup B&B reactor is defined as one in which neutron leakage is minimized and feed fuel can be discharged at uniform burnup. The neutron excess concept reformulates the k-effective of a system in terms of material depletion quantities: the total number of neutrons absorbed and produced by a given volume of fuel, which are termed "neutron excess quantities". This concept is useful because neutron excess quantities are straightforward to estimate using simple 1D and 0D models. A set of equations is developed which allows the quantity of starter fuel needed to establish a given B&B equilibrium cycle to be expressed in terms of neutron excess quantities. A simple 1D example of a sodium cooled, metal fuel reactor with a startup enrichment of 15% is used to illustrate how the method is applied. An estimate for the required amount of starter fuel based on a 0D depletion model is found to differ by only 3% from the actual amount computed using the 1D example model.

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Design study of 208Pb-Bi eutectic-cooled reactor with natural uranium as fuel cycle input with radial fuel shuffling

Widiawati

Su’ud

Irwanto

et al. 2022

Annals of Nuclear Energy

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“CANDLE” burnup regime after LWR regime

Cited by 9 publications

References 5 publications

Application of Modified CANDLE Burnup to Very Small Long Life Gas-Cooled Fast Reactor

Application of Modified CANDLE Burnup to Very Small Long Life Gas-Cooled Fast Reactor

Using the Neutron Excess Concept to Determine Starting Fuel Requirements for Minimum Burnup Breed-and-Burn Reactors

Design study of 208Pb-Bi eutectic-cooled reactor with natural uranium as fuel cycle input with radial fuel shuffling

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