Evaluation of RAPID for a UNF cask benchmark problem-Reference-Cited by-同舟云学术

Evaluation of RAPID for a UNF cask benchmark problem

Published:2017 Issue: Volume:153 Page:05025
ISSN:2100-014X
Container-title:EPJ Web of Conferences
language:
Short-container-title:EPJ Web Conf.

Author:

Mascolino Valerio,Haghighat Alireza,Roskoff Nathan J.

Publisher

EDP Sciences

Link

http://www.epj-conferences.org/10.1051/epjconf/201715305025/pdf

Reference11 articles.

1. Haghighat A., Monte Carlo Methods for Particle Transport (CRC Press Taylor & Francis Group, 2015)

2. A Fission Matrix Based Methodology for Achieving an Unbiased Solution for Eigenvalue Monte Carlo Simulations

3. Fission matrix based Monte Carlo criticality calculations

4. Walters W., Roskoff N.J., Haghighat A., A Fission Matrix Approach to Calculate Pin-wise 3D Fission Density Distribution, in Proc. M&C 2015 (Nashville, Tennesse, 2015)

5. MRT methodologies for real-time simulation of nonproliferation and safeguards problems

Cited by 18 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Experimental validation of the 3-D neutron kinetics algorithm of RAPID using the JSI TRIGA Mark-II reactor;Progress in Nuclear Energy;2024-11

2. A reduced order model discretisation of the space-angle phase-space dimensions of the Boltzmann transport equation with application to nuclear reactor problems;Journal of Computational Physics;2024-11

3. Development of a Predictor-Corrector Quasi-Static Transient Fission Matrix combination method for the neutronics transient simulation;Nuclear Engineering and Design;2024-08

4. Verification of a novel fuel burnup algorithm in the RAPID code system based on Serpent-2 simulation of the TRIGA Mark II research reactor;Nuclear Engineering and Technology;2023-10

5. A Novel Hybrid Deterministic and Monte Carlo Neutron Transport Formulation and Algorithm (tRAPID) for Accurate and Fast 3-D Reactor Kinetics;Nuclear Science and Engineering;2023-05-26