Properties of unirradiated fuel element graphites H-451 and TS-1240

Johnson, W. R.; Engle, Genevieve

doi:10.2172/7283150

Cited by 4 publications

(3 citation statements)

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“…Nuclear реактор within the framework of GT-MHR reactor design project (GT-MHR 2002, Vasyaev et al 2001, Neylan et al 1994, Engle 1977, Engle and Johnson 1976 is the pressurized graphite-gas high-temperature reactor with helium coolant and thermal power of the core equal to 600 MW. Reactor core is shaped as a hexagonal collar and consists of fuel assemblies in the form of perforated prismatic hexagonal blocks.…”

Section: Generic Physical Model Of the Processmentioning

confidence: 99%

Temperature field in gas-cooled reactor core in transient conditions under different approaches to mass flow profiling

Kuzevanov¹,

Podgorny²

2019

NUCET

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Positive effect of profiling the gas-cooled reactor core within the framework of the GT-MHR project was investigated in (Podgorny and Kuzevanov 2017, Kuzevanov and Podgorny 2017, 2018). The necessity arises to supplement already implemented analysis of equilibrium conditions of core operation with investigation of effects of profiling on the temperature field in transient modes of reactor core operation. The present paper is dedicated to the investigation of development of transients in gas-cooled nuclear reactor core subject to the implementation of different principles of core profiling. Investigation of transients in reactor core represents complex problem, solution of which by conducting direct measurements is beyond the resources available to the authors. Besides the above, numerical simulation based on advanced CFD software complexes (ANSYS 2016, 2016a, 2016b, Shaw 1992, Anderson et al. 2009, Petrila and Trif 2005, Mohammadi and Pironneau 1994) is also fairly demanding in terms of required computer resources. The algorithm for calculating temperature fields using the model where the reactor core is represented as the solid medium with gas voids was developed by the authors and the assumption was made that heat transfer due to molecular heat conductivity can be described by thermal conductivity equation written for continuous medium with thermal physics parameters equivalent to respective parameters of porous object in order to get the possibility of obtaining prompt solutions of this type of problems. Computer code for calculating temperature field in gas-cooled reactor in transient operation modes was developed based on the suggested algorithm. Proprietary computation code was verified by comparing the results of numerous calculations with results of CFD-modeling of respective transients in the object imitating the core of gas-cooled nuclear reactor. The advantage of the developed computer code is the possibility of real-time calculation of evolution of conditions in complex configurations of gas-cooled reactor cores with different channel diameters. This allows using the computer code in the calculations of transients in loops of reactor facility as a whole, in particular for developing reactor simulators. Results are provided of calculations of transients for reactor core imitating the core of gas-cooled nuclear reactor within the framework of GT-MHR project performed for different approaches to profiling coolant mass flow. Results of calculations unambiguously indicate the significant difference of temperature regimes during transients in the reactor core with and without profiling and undeniable enhancement of reliability of nuclear reactor (Design of the Reactor Core 2005, International Safeguards 2014, Safety of Nuclear Power Plants 2014) with profiling of coolant mass flow in the reactor core as a whole.

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Section: Generic Physical Model Of the Processmentioning

confidence: 99%

Temperature field in gas-cooled reactor core in transient conditions under different approaches to mass flow profiling

Kuzevanov¹,

Podgorny²

2019

NUCET

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“…Tensile stress-strain curves were obtained in ambient air at room temperature using a standard method described in Ref. 4.…”

Section: Strength Elastic Modulus and Strain-at-fracture Measurementsmentioning

confidence: 99%

“…This chord modulus represents the effective modulus of a graphite component after its first strain excursion (see Ref. 4…”

Section: Strength Elastic Modulus and Strain-at-fracture Measurementsmentioning

confidence: 99%

Effect of steam oxidation on strength, elastic modulus, and strain at fracture of graphite 2020. [HTGR]

Velasquez¹,

Hightower²,

Burnette³

1977

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Stackpole Carbon's graphite grade 2020, a candidate material for support posts in GA HTGRs, was oxidized in steam-helium mixtures to 25 wt % burnoff. The effects of the oxidation on ultimate strength, elastic modulus, and strain at fracture are reported. A large number of nonoxidized and oxidized tensile specimens were tested to failure. Average losses of 6.7 wt % in strength and 7.4 wt % in elastic modulus at 1% burnoff were obtained. No significant change in strain at fracture was observed for burnoffs up to 5%. The elastic modulus and ultimate tensile strength of the oxidized samples correlated with bulk density. No significant radial gradients in strength or elastic modulus were observed in the log; however, slight differences in elastic modulus and strain at fracture were observed along the length of the log. Radial specimens had significantly higher strength and elastic modulus than axial specimens.

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