Title :
Modeling reactors with AGENT: Verification, validation, efficiency analysis and 3D-Visuals on iPod
Author :
Xiao, Shanjie ; Yang, Xue ; Satvat, Nader ; Jevremovic, Tatjana
Author_Institution :
Nucl. Eng. Program, Univ. of Utah, Salt Lake City, UT, USA
Abstract :
The existing various reactor physics computational tools are capable of performing analysis of current (research and power) reactors to a certain level of details with many of them introducing simplifications and assumptions dependent on neutron transport method introduced and methodology for describing reactor geometries. Such approaches for over forty years produced accurate analysis for currently operating light water reactors. But there is a GenIV group of reactor designs that is yet to be analyzed and possibly some of them built. All disciplines aggressively are taking the advantage of fast computer development pertaining to computer hardware performances, in advancing and probing new directions in developments with the aim of capturing details of physics phenomena and processes in various complex systems. Among such computational and numerical attempts, based on advanced numerical and analytical methodologies which enable us to overcome simplifications and assumptions, it is found currently that the most advanced and accurate deterministic method simulating the neutron transport, is the method of characteristics that can capture easily details of the 2D/3D neutron transport. In addition, this method allows also an easy modeling of higher order of neutron anisotropic transport in complex geometries. Because the methodology does not ask for any simplifications in geometry, the visuals of neutron transport and reactor physics parameters is easy to achieve given enough computer memory and speed to process sometimes TB size data. This paper presents the state-of-the-art AGENT methodology in validating and verifying efficiency of neutron transport in general-geometry nuclear reactor assemblies taking into account the effects of anisotropic scattering. Additionally we present a new approach in accelerating the neutron transport modeling using the FPGA (Field Programmable Gate Array) chip. The overview of the validated and verified capabilities of AGENT inclusive of F- - PGA design description is presented using a heterogeneous small assembly configuration derived from well known C5G7 benchmark. And, the complex, data extensive, plots of 3D spatial flux, reaction rates or power distributions can be available on your iPod/iPhone. Various possibilities of high quality graphics representing direct display of reactor simulations on iPods will be demonstrated at the conference. AGENT is an integral part of our on-line experiential undergraduate and graduate educational modules; these modules are part of our courses pertaining to reactor physics and computational reactors´ simulations.
Keywords :
field programmable gate arrays; fission reactor design; light water reactors; neutron transport theory; nuclear engineering computing; 2D neutron transport simulation; 3D-visuals; AGENT methodology; C5G7 benchmark; FPGA design; GenIV group; complex systems; computational reactor simulation; computational tools; computer hardware performances; computer memory; efficiency analysis; light water reactor; neutron anisotropic transport; neutron transport method; nuclear reactor geometry; reactor design; reactor modeling; Anisotropic magnetoresistance; Assembly; Computational geometry; Computational modeling; Field programmable gate arrays; Inductors; Neutrons; Performance analysis; Physics computing; Portable media players;
Conference_Titel :
Nuclear & Renewable Energy Conference (INREC), 2010 1st International
Conference_Location :
Amman
Print_ISBN :
978-1-4244-5213-2
Electronic_ISBN :
978-1-4244-5214-9
DOI :
10.1109/INREC.2010.5462575