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Thermodynamic Modeling of Uranium Mo...

McManus, Eric Reece,

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Thermodynamic Modeling of Uranium Mononitride With Select Actinides and Fission Products /

紀錄類型:	書目-電子資源 : Monograph/item
正題名/作者:	Thermodynamic Modeling of Uranium Mononitride With Select Actinides and Fission Products // Eric Reece McManus.
作者:	McManus, Eric Reece,
面頁冊數:	1 electronic resource (53 pages)
附註:	Source: Masters Abstracts International, Volume: 86-02.
Contained By:	Masters Abstracts International86-02.
標題:	Mechanical engineering. -
電子資源:	https://pqdd.sinica.edu.tw/twdaoapp/servlet/advanced?query=30993148
ISBN:	9798383681480

Thermodynamic Modeling of Uranium Mononitride With Select Actinides and Fission Products /
McManus, Eric Reece,

Thermodynamic Modeling of Uranium Mononitride With Select Actinides and Fission Products /Eric Reece McManus. - 1 electronic resource (53 pages)

Source: Masters Abstracts International, Volume: 86-02.

Uranium mononitride fuel is being investigated as a potential nuclear fuel for a Westinghouse lead-cooled fast reactor due to factors such as its high uranium density, high melting point, and favorable thermal conductivity. To obtain an understanding of the thermochemical behavior of UN fission products and minor actinides, thermodynamic data was obtained from various resources to create a database to represent the behavior of the fuel. This database was used to generate an Ellingham diagram to represent the relative thermodynamic stability of the phases over the reactor temperature range. A simulation was run computing the equilibrium state of the fuel, using the model comprised of all the potential phases based on the fuel's composition at a burnup of 60MWd/kgU, over the temperature range of 800K-2100K to observe the formation of these phases. This model simulation yielded information on what solutions were present, the amount of these solutions, and their composition at each temperature step. In analyzing the results from the simulation, at a temperature of 1520K the sesquinitride phase ceases to be present, the FCC phase reaches its maximum concentration at 1520K before slowly decreasing over the remainder of the temperature range, and the content of UN in the reactor reaches its peak value at 1540K and maintains it. Additionally, more research is needed into the fission product nitride systems to understand their interaction parameters within the FCC solution so as not to be assumed an ideal solution and to gather data on the systems that were unable to be represented (and those that were used as surrogates) to provide a more accurate model of the fuel.

English

ISBN: 9798383681480Subjects--Topical Terms:

649730
Mechanical engineering.
Subjects--Index Terms:

Uranium mononitride

Thermodynamic Modeling of Uranium Mononitride With Select Actinides and Fission Products /
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520 $a Uranium mononitride fuel is being investigated as a potential nuclear fuel for a Westinghouse lead-cooled fast reactor due to factors such as its high uranium density, high melting point, and favorable thermal conductivity. To obtain an understanding of the thermochemical behavior of UN fission products and minor actinides, thermodynamic data was obtained from various resources to create a database to represent the behavior of the fuel. This database was used to generate an Ellingham diagram to represent the relative thermodynamic stability of the phases over the reactor temperature range. A simulation was run computing the equilibrium state of the fuel, using the model comprised of all the potential phases based on the fuel's composition at a burnup of 60MWd/kgU, over the temperature range of 800K-2100K to observe the formation of these phases. This model simulation yielded information on what solutions were present, the amount of these solutions, and their composition at each temperature step. In analyzing the results from the simulation, at a temperature of 1520K the sesquinitride phase ceases to be present, the FCC phase reaches its maximum concentration at 1520K before slowly decreasing over the remainder of the temperature range, and the content of UN in the reactor reaches its peak value at 1540K and maintains it. Additionally, more research is needed into the fission product nitride systems to understand their interaction parameters within the FCC solution so as not to be assumed an ideal solution and to gather data on the systems that were unable to be represented (and those that were used as surrogates) to provide a more accurate model of the fuel.
546 $a English
590 $a School code: 0202
650 4 $a Mechanical engineering. $3 649730
650 4 $a Thermodynamics. $3 517304
653 $a Uranium mononitride
653 $a Nuclear fuel
653 $a Thermodynamic data
653 $a UN fission products
690 $a 0548
690 $a 0348
710 2 $a University of South Carolina. $b Mechanical Engineering. $e degree granting institution. $3 3816294
720 1 $a Besmann, Theodore $e degree supervisor.
773 0 $t Masters Abstracts International $g 86-02.
790 $a 0202
791 $a M.S.
792 $a 2024
856 4 0 $u https://pqdd.sinica.edu.tw/twdaoapp/servlet/advanced?query=30993148