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Title: Theoretical analysis of integral neutron transport equation using collision probability method with quadratic flux approach

Theoretical analysis of integral neutron transport equation using collision probability (CP) method with quadratic flux approach has been carried out. In general, the solution of the neutron transport using the CP method is performed with the flat flux approach. In this research, the CP method is implemented in the cylindrical nuclear fuel cell with the spatial of mesh being conducted into non flat flux approach. It means that the neutron flux at any point in the nuclear fuel cell are considered different each other followed the distribution pattern of quadratic flux. The result is presented here in the form of quadratic flux that is better understanding of the real condition in the cell calculation and as a starting point to be applied in computational calculation.
Authors:
; ; ;  [1] ;  [2] ;  [3]
  1. Department of Physics, Andalas University Padang West Sumatera Indonesia (Indonesia)
  2. Department of Physics, Sam Ratulangi University Manado North Sulawesi Indonesia (Indonesia)
  3. Department of Physics, Jember University Jember East Java Indonesia (Indonesia)
Publication Date:
OSTI Identifier:
22307877
Resource Type:
Journal Article
Resource Relation:
Journal Name: AIP Conference Proceedings; Journal Volume: 1615; Journal Issue: 1; Conference: ICANSE 2013: 4. international conference on advances in nuclear science and engineering, Denpasar, Bali (Indonesia), 16-19 Sep 2013; Other Information: (c) 2014 AIP Publishing LLC; Country of input: International Atomic Energy Agency (IAEA)
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; COLLISION PROBABILITY METHOD; COLLISIONS; CYLINDRICAL CONFIGURATION; INTEGRAL EQUATIONS; NEUTRON FLUX; NEUTRON TRANSPORT; NEUTRON TRANSPORT THEORY; NUCLEAR FUELS; PROBABILITY