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Title: Advances in reactor physics education: Visualization of reactor parameters

Modern computer codes allow detailed neutron transport calculations. In combination with advanced 3D visualization software capable of treating large amounts of data in real time they form a powerful tool that can be used as a convenient modern educational tool for reactor operators, nuclear engineers, students and specialists involved in reactor operation and design. Visualization is applicable not only in education and training, but also as a tool for fuel management, core analysis and irradiation planning. The paper treats the visualization of neutron transport in different moderators, neutron flux and power distributions in two nuclear reactors (TRIGA type research reactor and a typical PWR). The distributions are calculated with MCNP and CORD-2 computer codes and presented using Amira software. (authors)
Authors:
; ;  [1]
  1. Josef Stefan Inst., Jamova cesta 39, SI-1000 Ljubljana (Slovenia)
Publication Date:
OSTI Identifier:
22105679
Resource Type:
Conference
Resource Relation:
Conference: PHYSOR 2012: Conference on Advances in Reactor Physics - Linking Research, Industry, and Education, Knoxville, TN (United States), 15-20 Apr 2012; Other Information: Country of input: France; 11 refs.
Publisher:
American Nuclear Society - ANS; La Grange Park, IL (United States)
Research Org:
American Nuclear Society, Inc., 555 N. Kensington Avenue, La Grange Park, Illinois 60526 (United States)
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; CARBON MONOXIDE; COMPUTER CODES; COMPUTER GRAPHICS; DESIGN; EDUCATIONAL TOOLS; FLOW VISUALIZATION; FUEL MANAGEMENT; MODERATORS; MONTE CARLO METHOD; NEUTRON FLUX; NEUTRON TRANSPORT; PARTICLE TRACKS; PWR TYPE REACTORS; REACTOR OPERATION; REACTOR OPERATORS; REACTOR PHYSICS; RESEARCH REACTORS; THREE-DIMENSIONAL CALCULATIONS; TRAINING; TRIGA TYPE REACTORS