Neutron interaction and their transport with bulk materials

Journal Article · Fri May 15 00:00:00 EDT 2015 · AIP Conference Proceedings

DOI:https://doi.org/10.1063/1.4915462· OSTI ID:22391772

Rani, Esther Kalpana, E-mail: [e-mail] ^[1]; Radhika, K., E-mail: [e-mail] ^[2]

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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)

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.

• OSTI ID: 22391772
• Journal Information: AIP Conference Proceedings, Vol. 1661, 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); ISSN 0094-243X
• Country of Publication: United States
• Language: English

Related Subjects

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