A methodology to enhance thermal neutron flux in Tehran Research Reactor core for domestic fuel test purposes-Reference-Cited by-同舟云学术

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A methodology to enhance thermal neutron flux in Tehran Research Reactor core for domestic fuel test purposes

Published:2021-06 Issue: Volume:136 Page:103726
ISSN:0149-1970
Container-title:Progress in Nuclear Energy
language:en
Short-container-title:Progress in Nuclear Energy

Author:

Safaei Arshi S.,Jozvaziri A.,Mirvakili S.M.,Keyvani M.

Publisher

Elsevier BV

Subject

Waste Management and Disposal,Energy Engineering and Power Technology,Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering

Reference11 articles.

1. Safety Analysis Report of Tehran Research Reactor,2018

2. Operational Limits and Conditions (OLCs) of TRR,2010

3. CAUDVAP V 3.60: A Computer Program for Flow Distribution and Pressure Drop Calculation in a MTR Type Core;Abbate,2003

4. TERMIC V 4.1: A Program for the Calculus and Thermal-Hydraulic Design of Research Reactor Cores;Abbate,2003

5. Feasibility study for tehran research reactor power upgrading;Farhadi;Ann. Nucl. Energy,2008

Cited by 2 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. Core reduction for increasing neutron flux and radioisotope production in the IEA-R1 research reactor;Nuclear Engineering and Design;2024-05

2. Development of distributed and automated system for 14MeV neutron generator laboratory;Radiation Physics and Chemistry;2022-04

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