Neutronics Analysis of Pressurized Water Reactor Cores using IDEA Code [version 1; peer review: 2 approved]

Neutronics Analysis of Pressurized Water Reactor Cores using IDEA Code [version 1; peer review: 2 approved]

Background This paper discusses the development and benchmarking of IDEA (Indigenous Diffusion Equation Analyzer), an in-house transient, multi-group, 3-dimensional neutron diffusion equation (NDE) code. IDEA can perform both steady-state criticality calculations and reactivity transient analysis fo...

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Bibliographic Details
Main Authors: Ubaid ur Rehman, Zahid Rasool, M. Jawad Hussain, Ali Mansoor, Farhana Kausar, Haseeb ur Rehman, Aman ur Rehman
Format: Article
Language:English
Published: F1000 Research Ltd 2025-01-01
Series:Nuclear Science and Technology Open Research
Subjects:
neutron diffusion equation
finite difference method
PRIDE
CITATION
steady state
and transient reactivity benchmarks.
eng
Online Access:https://nstopenresearch.org/articles/3-4/v1
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https://nstopenresearch.org/articles/3-4/v1

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