The application of UWB1 nuclear fuel depletion code on a CANDU fuel bundle

Lovecký, Martin; Škoda, Radek; Hussein, M.S.; Song, Jason J.; Chan, Paul K.

doi:10.1016/j.pnucene.2016.03.010

Cited by 3 publications

(1 citation statement)

References 5 publications

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“…Multiplication factors in the depletion steps other than the first and the last one are estimated by neutron production to absorption ratio that is calculated without the need to call the transport solver. The U W B 1 nuclear fuel depletion code was the most intensively validated against other codes for the CANDU fuel bundle (Lovecký et al, 2016); the comparison study included WIMS, MCNP6, Serpent, KENO-VI and NEWT codes. The behaviors of all investigated parameters were captured by the code.…”

Section: U W B 1 Codementioning

confidence: 99%

Increasing efficiency of nuclear fuel using burnable absorbers

Lovecký

Závorka

Jiřičková

et al. 2020

Progress in Nuclear Energy

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The paper describes the development, validation, and use of U W B 1 code intended for fast calculation of nuclear fuel depletion in burnable absorber research. The degree of effectiveness of burnable absorbers in the form of natural abundance elements, nuclides, and their combinations are compared on metric evaluating characteristic properties of burnable absorbers; namely the initial reactivity compensation, residual poisoning minimization, and the influence of the fuel reactivity for higher fuel burnups. The following materials suitable for burnable absorbers are recommended: Li, Pa, Ir, In and Re, as well as perspective of Li-6 enrichment; beside previously commonly studied boron and rare earth metals. The research results are intended for the application in other technical-economical analyses of the selection of added materials in the nuclear fuel for increasing the fuel efficiency and nuclear safety.

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Section: U W B 1 Codementioning

confidence: 99%

Increasing efficiency of nuclear fuel using burnable absorbers

Lovecký

Závorka

Jiřičková

et al. 2020

Progress in Nuclear Energy

Self Cite

View full text Add to dashboard Cite

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Differences in Exit Burnup, Depletion, and Fuel Reactivity Calculations Arising From the Choice of Modelling Code for Bundles With Thorium and Uranium

2020

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A computational benchmark, using the deterministic codes WIMS-AECL and WOBI, and the stochastic code SERPENT, is made for burnup calculations of advanced thorium fuels in heavy water moderated reactors. Exit burnups and the concentration of the longer-lived actinides from the deterministic code set of WIMS-AECL and WOBI, which are 2-D, were compared to those from a full 3-D calculation in SERPENT. Results for reactivity vs. time are in general agreement to within a few mk (<1% in overall neutron multiplication) and appear to be systematic. Results for exit burnup were larger, in the 3%–6% range, because small reactivity effects can be amplified here.

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