These data contain the Serpent and RAPID transport calculation results on the BEAVRS benchmark with four distributions of temperature, including: 1. Only heterogeneous fuel temperature 2. Only hetero

NIAID Data Ecosystem70

Development of A Coupled Neutron Kinetics And Thermal Hydraulics Code With 3-D Two Group Neutron Kinetics Solver and OpenFOAM by Adding Feedback of Coolant Temperature in Calculation of Cross Section Using DRAGON for Pressurized Heavy Water Reactor

核反应堆物理模拟

重水堆安全分析

A loosely coupled reactor is subject to local perturbations due to reactivity device movement that affects the neutron kinetics in a local region of the reactor core. Pressurized Heavy Water Reactor (

Mendeley Data40

A deterministic transport calculation method of α-eigenvalue for non-multiplying system using framework of k-eigenvalue calculation

中子输运计算

核反应堆物理模拟

A new α-eigenvalue calculation method for a non-multiplying system using the framework of conventional k-eigenvalue calculation of a deterministic transport code is proposed. The time-derivative or th

Figshare2025-05-21 更新70

Data for: material-region-based 2D1D transport method

核反应堆物理模拟

中子输运计算

Results

NIAID Data Ecosystem60