Analysis, Colligation, and Investigation of the Thermal Conductivity of Fuel Compositions Based on Uranium Mononitride

Vybyvanets, V.I.; Taubin, M. L.; Solntseva, E.S.; Galev, I. E.; Баранов, В. Г.; Tenishev, A. V.; Khomyakov, O. V.

doi:10.1007/s10512-015-9919-3

Cited by 4 publications

(4 citation statements)

References 13 publications

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“…This effect, especially in UN, is found to persist even after electronic contributions to thermal transport from 5f electrons are considered. 5 The removal of the dampening effect of oxygen is substantial: the thermal conductivity of UN is 4-8 times greater than that of UO 2 in the temperature range relevant to the steady-state operation of a nuclear reactor. Previous investigations have suggested that ThN has a thermal conductivity at room temperature in the range of 40-50 W/(mK).…”

Section: Introductionmentioning

confidence: 99%

Thermophysical Properties of Mixtures of Thorium and Uranium Nitride

Parker

Newman

Fallgren

et al. 2021

JOM

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The miscibility, lattice parameter, and thermophysical properties of (Th0.2U0.8)N and (Th0.5U0.5)N have been investigated. It is shown that additions of thorium nitride (ThN) to uranium nitride (UN) increases the thermophysical performance of the mixed nitride fuel form in comparison to reference UN. In the more dilute limit, additions of ThN serve as a burnable neutronic poison and reduces the change in keff over the lifecycle of the fuel. At higher concentrations, additions of ThN serve as a significant fertile source of 233U. Where appropriate, comparisons to previous work on UN + PuN mixtures are made, as this is a comparable fuel form for potential fast reactor concepts, and a suitable point of contrast in the possible design space afforded by mixed (ThxU1 − x)N fuel forms. The data from this work are the input parameters for finite element modeling of the temperature distribution in a compact reactor. The results of modeling and simulation of this core design are shown for the case of steady-state operation and during double, adjacent heat pipe failure.

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Section: Introductionmentioning

confidence: 99%

Thermophysical Properties of Mixtures of Thorium and Uranium Nitride

Parker

Newman

Fallgren

et al. 2021

JOM

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“…This choice of material is motivated, in part, by the higher actinide density and significantly improved thermophysical properties compared with reference oxide and carbide fuels. [10][11][12][13][14][15][16][17] In comparison to oxide or mixed oxide fuels, non-oxide ceramic fuels (i.e., carbides, nitrides, silicides) have marginally lower melting points but significantly higher thermal conductivity. [11][12][13] In particular, ThN and UN have favorable thermophysical properties for reactor applications and the properties and applications of mixtures of this material are the subject of ongoing research.…”

Section: Introductionmentioning

confidence: 99%

“…[10][11][12][13][14][15][16][17] In comparison to oxide or mixed oxide fuels, non-oxide ceramic fuels (i.e., carbides, nitrides, silicides) have marginally lower melting points but significantly higher thermal conductivity. [11][12][13] In particular, ThN and UN have favorable thermophysical properties for reactor applications and the properties and applications of mixtures of this material are the subject of ongoing research. 11,14,18 For the case of fixed linear power density from fission across the fuel and for the same period of fuel burnup, the increase in thermal conductivity associated with switching from oxide to nitride fuels results in reduced centerline temperatures and a reduction in the thermal gradients.…”

Section: Introductionmentioning

confidence: 99%

“…The thermal and mechanical properties of UN and, to a limited extent, (U x Pu 1Àx )N, have been measured as a function of temperature and pressure. 15,[27][28][29] A comprehensive summary of these material properties is presented in, 29 and is used as a key reference for point of comparison. Irradiation testing of UN and mixed UN and PuN has been carried out over the past few decades.…”

Section: Introductionmentioning

confidence: 99%

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Neutronic Performance of a Compact 10 MWe Nuclear Reactor with Low Enrichment (ThxU1−x)N Fuel

Parker

Newman

Fallgren

2021

JOM

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Recent interest in compact nuclear reactors for applications in space or in remote locations drives innovation in nuclear fuel design, especially non-oxide ceramic nuclear fuels. This work details neutronic modeling designed to support the development of a new nuclear fuel concept based on a mixture of thorium and uranium nitride. A Monte Carlo N-Particle Version 6.2 (MCNP-6) model of a compact 10 MWe reactor design which incorporates (ThxU1−x)N fuel is presented. In this context, a “compact” reactor is a completely assembled reactor which may be emptied of coolant and transported by specialized commercial vehicle, deployed by a C130J aircraft, or launched into space. Core geometry, reflector barrels, and the heat exchange zones are designed to support reduction of overall reactor volume of core components while maintaining criticality with a fixed total fuel mass of 4500 kg. Dense mixed nitrides of thorium nitride (ThN) additions in uranium nitride (UN) in 5 wt.% increments between $$0.05 \le x \le 0.5$$ 0.05 ≤ x ≤ 0.5 have been considered for calculation of $$k_{\infty }$$ k ∞ and $$k_{{{\text{effective}}}}$$ k effective . ThN additions in UN results in a slight increase in the magnitude of the temperature coefficient of reactivity, which is negative by design. The isotopic distribution of the principal actinide inventory as a function of burnup, time, and initial fuel composition is presented and discussed within the context of the proliferation risk of this core design.

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Other power reactor fuels

Nelson

Demkowicz

2020

Advances in Nuclear Fuel Chemistry

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Analysis, Colligation, and Investigation of the Thermal Conductivity of Fuel Compositions Based on Uranium Mononitride

Cited by 4 publications

References 13 publications

Thermophysical Properties of Mixtures of Thorium and Uranium Nitride

Thermophysical Properties of Mixtures of Thorium and Uranium Nitride

Neutronic Performance of a Compact 10 MWe Nuclear Reactor with Low Enrichment (ThxU1−x)N Fuel

Other power reactor fuels

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