Calculation of neutron flux and neutron visualization in a spherical reactor core applying a conceptual approach and drawing a comparison with the results obtained by the CITATION code-Reference-Cited by-同舟云学术

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Calculation of neutron flux and neutron visualization in a spherical reactor core applying a conceptual approach and drawing a comparison with the results obtained by the CITATION code

Published:2021 Issue: Volume:3 Page:166-174
ISSN:2468-6050
Container-title:International Journal of Advanced Nuclear Reactor Design and Technology
language:en
Short-container-title:International Journal of Advanced Nuclear Reactor Design and Technology

Author:

Mousavi Shirazi Seyed Alireza^ORCID

Publisher

Elsevier BV

Subject

General Medicine

Reference14 articles.

1. The effect of local power increase on neutron flux in internal parts of the VVER-1000 Mock-Up in LR-0 reactor;Košt'ál;Ann. Nucl. Energy,2018

2. The influence of core power distribution on neutron flux density behind a pressure vessel of a VVER-1000 Mock up in LR-0 reactor;Košt'ál;Appl. Radiat. Isot.,2018

3. Nuclear Reactor Core Analysis Code: CITATION, ORNL-TM-2496;Fowler,1971

4. Polyethylene moderator optimized for increasing thermal neutron flux in the NASBEE accelerator-based neutron field;Ogawara;Radiat. Meas.,2020

5. Obtaining the neutronic and thermal hydraulic parameters of the VVER-1000 Bushehr nuclear reactor core by coupling nuclear codes;Rafiei Karahroudi;Kerntechnik,2014

Cited by 1 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. Assessment of the IEA-R1 nuclear reactor using a nonstandard fuel assembly with six fuel plates of the Brazilian Multipurpose Reactor;Nuclear Engineering and Design;2024-05

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