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Title: Neutron interaction and their transport with bulk materials

In the current paper an attempt was made to study and provide fundamental information about neutron interactions that are important to nuclear material measurements. The application of this study is explained about macroscopic interactions with bulk compound materials through a program in DEV C++ language which is done by enabling interaction of neutrons in nature. The output of the entire process depends upon the random number (i.e., incident neutron number), thickness of the material and mean free path as input parameters. Further the current study emphasizes on the usage of materials in shielding.
Authors:
 [1] ;  [2]
  1. Department of Physics JNT University, Nachupally, Karimnagar, Telangana, 500055 (India)
  2. Department of Humanities and Applied Sciences, Talla Padmavathi College of Engineering, Warangal, Telangana, 506004 (India)
Publication Date:
OSTI Identifier:
22391772
Resource Type:
Journal Article
Resource Relation:
Journal Name: AIP Conference Proceedings; Journal Volume: 1661; Journal Issue: 1; Conference: ICCMP 2014: International Conference on Condensed Matter Physics 2014, Shimla (India), 4-6 Nov 2014; Other Information: (c) 2015 AIP Publishing LLC; Country of input: International Atomic Energy Agency (IAEA)
Country of Publication:
United States
Language:
English
Subject:
71 CLASSICAL AND QUANTUM MECHANICS, GENERAL PHYSICS; 75 CONDENSED MATTER PHYSICS, SUPERCONDUCTIVITY AND SUPERFLUIDITY; COMPOSITE MATERIALS; COMPUTERIZED SIMULATION; MATRIX MATERIALS; MEAN FREE PATH; NEUTRON TRANSPORT; NEUTRONS; PARTICLE INTERACTIONS; RANDOMNESS; SHIELDING MATERIALS