Stochastic arranging of CFPs in HTTR and criticality benchmark considering different modeling of CFPs

Ardakani, Abbas Torabi; Ghofrani, M.; Ezzati, Ahad Ollah

doi:10.1016/j.nucengdes.2013.11.060

Cited by 5 publications

(2 citation statements)

References 2 publications

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“…Subsequently, the calculated values were then used as the input parameter for neutronic steady‐state calculation via the MCNPX 2.7 code 41 . It has been widely used to simulate and analyze the HTR core, including fuel burnup, in detail with a less simplified geometry model 42‐45 . Besides, this specific code could also simulate the stochastic arrangement of TRISO particles in the HTR compact fuel.…”

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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“…Monte Carlo code such as the Monte Carlo N‐Particle Transport (MCNP) is widely accepted as one of the advanced 3D neutronic design tools to simulate complicated reactor cores. The MCNP code, in fact, had been used to model and simulate the simplified HTR core 99,102‐104 . The code can even randomly arrange TRISO particles in the HTR fuel compact.…”

Section: Duplex Fuel Design For Htrmentioning

confidence: 99%

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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Neutronics calculation of the conceptual TRISO duplex fuel rod design

Rabir

Ismail

Yahya

2021

Nuclear Materials and Energy

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Stochastic arranging of CFPs in HTTR and criticality benchmark considering different modeling of CFPs

Cited by 5 publications

References 2 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

Neutronics calculation of the conceptual TRISO duplex fuel rod design

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