Monte Carlo burnup in HTR system with various TRISO packing

Kępisty, G.; Stanisz, Przemysław; Cetnar, Jerzy

doi:10.1016/j.anucene.2016.02.013

Cited by 15 publications

(5 citation statements)

References 21 publications

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“…This approach has been chosen due to the model simplicity. Moreover, the differences between the reported k eff of the regular cubic and stochastic arrangements are significantly small if the particle packing fractions were fixed at 30% or higher 42,46,47 . In this specific study, analysis of the fuel models was conducted based on a particle fraction of 30%.…”

Section: Methodsmentioning

confidence: 99%

A neutronic investigation of tristructural isotropic‐duplex fuel in a high‐temperature reactor prismatic seed‐and‐blanket fuel block configuration with reduced power peaking

2021

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Summary This paper presents the neutronic analysis of a tristructural isotropic (TRISO)‐duplex fuel loaded into the high‐temperature reactor (HTR) prismatic fuel block designs for a seed‐and‐blanket (S&B) reactor model. The selected fuel block design is the simplified model of a representative fuel configuration for the gas turbine–module helium reactor (GT‐MHR) and high‐temperature engineering test reactor (HTTR). The duplex fuel pellet comprises of UO2 as the seed and ThO2 as the blanket and uses the TRISO fuels. Monte Carlo N‐particle extended (MCNPX) simulations were conducted to analyze the power and neutron flux distributions of the reference fuel block and that of the TRIOS‐loaded duplex fuel designs. Standard neutronic parameters were computed, such as burnup‐dependent infinite multiplication factors (kinf), average block spectrum, and fissile inventory. It was discovered that while the S&B model could attain the highest burnup and the longest cycle duration, its power peaking was more than threefolds than that of the reference model at the beginning of the cycle (BOC). The results also show that the “Duplex‐2” model could reduce its power peaking by 24% through the integration of S&B arrangement with the duplex rods. It is noted that spatial distribution of the UO2 seed and 235U enrichment are the chief determining factors in the power optimization of the heterogeneous HTR prismatic fuel blocks loaded with thorium.

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Section: Methodsmentioning

confidence: 99%

A neutronic investigation of tristructural isotropic‐duplex fuel in a high‐temperature reactor prismatic seed‐and‐blanket fuel block configuration with reduced power peaking

2021

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“…The HTR systems are capable of various fuel cycle scenarios, including thorium cycles and deep burning of minor actinides 67 . Early HTR technology actually ran on a mixture of thorium and highly‐enriched uranium.…”

Section: Htrmentioning

confidence: 99%

“…In the case of solving with deterministic codes, simplifications are necessary to reduce the level of spatial heterogeneity. In the case of solving with Monte Carlo codes, detailed modelling of the complex reactor geometries may be possible at the expense of computing power and time 67 . Thereby, it is suggested that the burnup calculations to be performed using advanced 3‐D Monte Carlo codes to capture the fine heterogeneity of TRISO duplex fuel pellets.…”

Section: Duplex Fuel Design For Htrmentioning

confidence: 99%

“…Any simplification and homogenization of the graphite matrix and fuel kernels may lead to unaccounted yet significant calculation errors especially in the tailing of core isotopic compositions, effective multiplication factor (k eff ) and cycle length 97‐99 . To our advantage, systematic fuel particle modelling at the fuel rod level can help to expedite burnup simulations of the HTR systems, such as reduction of estimated CR value for the more advanced TRISO particle configuration compared to the homogenized or simplified arrangement 67 . However, the memory requirement and the long simulation time/required CPU power are common capacity issues of Monte Carlo codes for depletion simulation 100 .…”

Section: Duplex Fuel Design For Htrmentioning

confidence: 99%

“…The code can even randomly arrange TRISO particles in the HTR fuel compact. In comparison to simplified deterministic neutronic calculation, the 3D Monte Carlo code offers reliable detailed core analyses such as k eff differences between regular cubic and stochastic TRISO particle arrangement at various particle packing fractions 67,97,99 , as shown in Figure 12.…”

Section: Duplex Fuel Design For Htrmentioning

confidence: 99%

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Review of the microheterogeneous thoria‐urania fuel for micro‐sized high temperature reactors

2020

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Summary This paper presents a systematic review of the micro‐modular thorium‐fueled high temperature reactors (HTR) loaded with duplex fuel pellet design. Specifically, each unique criterion of the design is discussed separately in an attempt to understand the combined advantages of the proposed reactor. Micro modular HTRs have great potential as a source of electricity or industrial heat in the future. The use of thorium not only improves its economic performance and safety, but also prolongs its operation. Nevertheless, the traditional seed‐and‐blanket configuration would not be able to maximize the thorium fuel burnup. As such, a new tristructural‐isotopic (TRISO) fuel based on duplex pellet designs were proposed instead. It should be noted that these duplex pellets were not practical for pressurized water reactor (PWR) technology due to its uneven power distribution which possibly leads to a very high local pellet temperature. However, this unorthodox inherent characteristics of the duplex pellets may actually suit the HTR burnup profile better due to its substantially higher thermal margin ‐ thus possibly enabling a relatively long operation of the HTR. The paper shall thereby provide a reasonably sound justification for the detailed technical investigations of the proposed reactor design.

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The impact of refueling schemes on the proliferation resistance of a pebble bed reactor

Mulyana

Chirayath

2022

Annals of Nuclear Energy

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Monte Carlo burnup in HTR system with various TRISO packing

Cited by 15 publications

References 21 publications

A neutronic investigation of tristructural isotropic‐duplex fuel in a high‐temperature reactor prismatic seed‐and‐blanket fuel block configuration with reduced power peaking

A neutronic investigation of tristructural isotropic‐duplex fuel in a high‐temperature reactor prismatic seed‐and‐blanket fuel block configuration with reduced power peaking

Review of the microheterogeneous thoria‐urania fuel for micro‐sized high temperature reactors

The impact of refueling schemes on the proliferation resistance of a pebble bed reactor

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