Abstract/Details

Multiphysics methods development for high temperature gas reactor analysis


2007 2007

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Abstract (summary)

Multiphysics computational methods were developed to perform design and safety analysis of the next generation Pebble Bed High Temperature Gas Cooled Reactors. A suite of code modules was developed to solve the coupled thermal-hydraulics and neutronics field equations. The thermal-hydraulics module is based on the three dimensional solution of the mass, momentum and energy equations in cylindrical coordinates within the framework of the porous media method. The neutronics module is a part of the PARCS (Purdue Advanced Reactor Core Simulator) code and provides a fine mesh finite difference solution of the neutron diffusion equation in three dimensional cylindrical coordinates. Coupling of the two modules was performed by mapping the solution variables from one module to the other. Mapping is performed automatically in the code system by the use of a common material mesh in both modules.

The standalone validation of the thermal-hydraulics module was performed with several cases of the SANA experiment and the standalone thermal-hydraulics exercise of the PBMR-400 benchmark problem. The standalone neutronics module was validated by performing the relevant exercises of the PBMR-268 and PBMR-400 benchmark problems. Additionally, the validation of the coupled code system was performed by analyzing several steady state and transient cases of the OECD/NEA PBMR-400 benchmark problem.

Indexing (details)


Subject
Nuclear engineering
Classification
0552: Nuclear engineering
Identifier / keyword
Applied sciences; Gas reactor; High-temperature; Nuclear reactors; PBR; Pebble bed reactor; Porous media
Title
Multiphysics methods development for high temperature gas reactor analysis
Author
Seker, Volkan
Number of pages
101
Publication year
2007
Degree date
2007
School code
0183
Source
DAI-B 69/04, Dissertation Abstracts International
Place of publication
Ann Arbor
Country of publication
United States
ISBN
9780549563662
Advisor
Downar, Thomas J.
Committee member
Bertodano, Martin A. Lopez De; Murthy, Jayathi Y.; Revankar, Shripad T.; Sameh, Ahmed H.
University/institution
Purdue University
Department
Nuclear Engineering
University location
United States -- Indiana
Degree
Ph.D.
Source type
Dissertations & Theses
Language
English
Document type
Dissertation/Thesis
Dissertation/thesis number
3307464
ProQuest document ID
304822461
Copyright
Database copyright ProQuest LLC; ProQuest does not claim copyright in the individual underlying works.
Document URL
http://search.proquest.com/docview/304822461
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