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SOLIDWORKS Based MCNP6 Reactor Criticality Calculation.

紀錄類型:	書目-語言資料,手稿 : Monograph/item
正題名/作者:	SOLIDWORKS Based MCNP6 Reactor Criticality Calculation./
作者:	Tumuluri, Madhuranath.
面頁冊數:	1 online resource (84 pages)
附註:	Source: Masters Abstracts International, Volume: 57-05.
標題:	Mechanical engineering. -
電子資源:	click for full text (PQDT)
ISBN:	9780355849028

SOLIDWORKS Based MCNP6 Reactor Criticality Calculation.
Tumuluri, Madhuranath.

SOLIDWORKS Based MCNP6 Reactor Criticality Calculation. - 1 online resource (84 pages)

Source: Masters Abstracts International, Volume: 57-05.

Thesis (M.S.)--Texas A&M University - Kingsville, 2017.

Includes bibliographical references

Reactor criticality calculation is one of the key steps in nuclear reactor design and development. Los Alamos National Laboratory has developed some codes to perform these calculations. One of the codes is MCNP6 (Monte Carlo N-Particle). The main objective of this research is to use SOLIDWORKS to design two reactor assemblies based on C5G7 benchmark model and calculate the criticality and pin power of the assemblies using MCNP6 and compare the results to C5G7 benchmark results. The C5G7 benchmark has very accurate Monte Carlo solutions for both two dimensional and three-dimensional configurations. In this work we consider two-dimensional assembly. MCNP6 is used in this work to perform reactor criticality modeling using Computer Aided Design (CAD) models designed in SOLIDWORKS. The CAD models are converted to ".DXF" files which are used by visual editing tool in MCNP6 to convert solid modeling data to MCNP6 understandable input format. MCNP6 package contains visual editor executable file called VISED which is used to view and edit the MCNP6 input file. In this research two assemblies are designed with different fuels. The models contain fuel-clad mix and moderator. Criticality factor "k-eff" and normalized pin power is calculated by executing the final input file. The results are compared to C5G7 geometry based MOCUM results and each pin power data is plotted using MATLAB data plotting feature.

Electronic reproduction.
Ann Arbor, Mich. :
ProQuest,
2018

Mode of access: World Wide Web

ISBN: 9780355849028Subjects--Topical Terms:

557493
Mechanical engineering.
Index Terms--Genre/Form:

554714
Electronic books.

SOLIDWORKS Based MCNP6 Reactor Criticality Calculation.
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245 1 0 $a SOLIDWORKS Based MCNP6 Reactor Criticality Calculation.
264 0 $c 2017
300 $a 1 online resource (84 pages)
336 $a text $b txt $2 rdacontent
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500 $a Source: Masters Abstracts International, Volume: 57-05.
500 $a Adviser: Xue Yang.
502 $a Thesis (M.S.)--Texas A&M University - Kingsville, 2017.
504 $a Includes bibliographical references
520 $a Reactor criticality calculation is one of the key steps in nuclear reactor design and development. Los Alamos National Laboratory has developed some codes to perform these calculations. One of the codes is MCNP6 (Monte Carlo N-Particle). The main objective of this research is to use SOLIDWORKS to design two reactor assemblies based on C5G7 benchmark model and calculate the criticality and pin power of the assemblies using MCNP6 and compare the results to C5G7 benchmark results. The C5G7 benchmark has very accurate Monte Carlo solutions for both two dimensional and three-dimensional configurations. In this work we consider two-dimensional assembly. MCNP6 is used in this work to perform reactor criticality modeling using Computer Aided Design (CAD) models designed in SOLIDWORKS. The CAD models are converted to ".DXF" files which are used by visual editing tool in MCNP6 to convert solid modeling data to MCNP6 understandable input format. MCNP6 package contains visual editor executable file called VISED which is used to view and edit the MCNP6 input file. In this research two assemblies are designed with different fuels. The models contain fuel-clad mix and moderator. Criticality factor "k-eff" and normalized pin power is calculated by executing the final input file. The results are compared to C5G7 geometry based MOCUM results and each pin power data is plotted using MATLAB data plotting feature.
533 $a Electronic reproduction. $b Ann Arbor, Mich. : $c ProQuest, $d 2018
538 $a Mode of access: World Wide Web
650 4 $a Mechanical engineering. $3 557493
650 4 $a Nuclear engineering. $3 655622
650 4 $a Design. $3 595500
655 7 $a Electronic books. $2 local $3 554714
690 $a 0548
690 $a 0552
690 $a 0389
710 2 $a ProQuest Information and Learning Co. $3 1178819
710 2 $a Texas A&M University - Kingsville. $b Mechanical and Industrial Engineering. $3 1187801
856 4 0 $u http://pqdd.sinica.edu.tw/twdaoapp/servlet/advanced?query=10788766 $z click for full text (PQDT)