Engineering Commons^™

A Review And Analysis Of Nuclear Hydrogen Production In Generation Iv Reactors, Arijit Saha Ayon, Ashiqur Rahman Alif, A. S. M. Nasim

International Journal of Nuclear Security

Hydrogen is becoming increasingly vital as a chemical element in the progress of human civilization. Hydrogen finds application in the creation of ammonia, the manufacturing of nitrogen-based fertilizers, and a wide range of organic compounds, including methanol and propulsion fuel for space exploration missions. Additionally, there are ongoing experiments in the automotive industry to harness hydrogen-based fuel cells as an alternative power source. In modern technology, multiple methods and strategies for hydrogen production originate from diverse sources, such as fossil fuels, renewable energy, nuclear energy, and more. Generation IV nuclear reactors significantly affect the production of hydrogen. These reactors operate …

Modeling And Analysis Of Neutron Flux Of A Vver 1200 Reactor Core Using Monte Carlo Code Openmc, K. M. Rakib Al Hasan, Dr. Debashis Datta, Altab Hossain

International Journal of Nuclear Security

Nuclear reactors and their associated facilities are complex systems that require accurate modeling and analysis to ensure safety, security, and efficient operation. This study aims to model and analyze the neutron flux of a generic VVER 1200 reactor core using the Monte Carlo code OpenMC. For the purpose of this analysis, a generic model of the VVER 1200 reactor core was developed using an OpenMC simulation environment. Furthermore, using this model, the neutron flux spectrum inside the reactor core was evaluated, from which neutron fluence was calculated accordingly. This study analyzed the effect of neutron flux on the developed model …

Safety And Security Analysis Of Vver-1200 Reactor Pressure Vessel Under Pressurized Thermal Shock, Mohammed Sarim Salman Karim, Dr. Debashis Datta, Altab Hossain

International Journal of Nuclear Security

The reactor pressure vessel (RPV) is an important component of a nuclear power plant and of great concern to safety and security globally. Thus, the thermal system of an RPV should be ensured properly through an evaluation system that closely monitors and considers its integrity. This article describes the thermomechanical analyses for a pressurized thermal shock (PTS) scenario of a VVER-1200 RPV owing to a loss of coolant accident (LOCA) and activation of the emergency core cooling system (ECCS). The LOCA transient and activation of ECCS are modeled using ANSYS simulation software. From the analyses of the emergency core cooling …

Design And Development Of A Radiation Survey And Rescue Robot With Shielding Of Electronic Equipment From Radiation Damage With Image Radiation Mapping Facility, Md. Sifatul Muktadir, Md. Nazmul Hassan, Md. Saimon Siddique, Dewan Nazmun Nur, Altab Hossain, Ahnaf Tahmid Chowdhury

International Journal of Nuclear Security

The use of remote-controlled robots in emergency fields is a necessary requirement at present, which includes the nuclear engineering field because the radioactive environment creates adverse effects on human health. This work describes the development of a remotely controlled rover capable of detecting ionizing radiation, isolating radiation sources using a robotic arm, and sufficient shielding for its internal components. A custom-made Geiger–Muller counter has been used to detect ionizing radiation. The radioactive environment is not only harmful for humans but also can cause severe damage to the electronic circuit mounted on the robot. Therefore, a custom concrete material sandwiched between …

Safety Analysis In Ap-1000 Nuclear Power Plant Against Primary Loop Coolant Pump And Fuel Failures, Fabiano Gibson Daud Thulu, Hailemichael Guadie Mengsitu, Chifundo Tenthani, Paul Stone Macheso

International Journal of Nuclear Security

This study focused on the best-estimated thermal-hydraulic calculations performed regarding the AP-1000 nuclear power plant (NPP) under primary coolant loop pump and fuel failures. Primary coolant pump and fuel failure transients are important design-basis accidents in NPP safety assessments. This work examined the primary reactor’s safety margins of fuel and cladding peak temperature, primary and secondary loop pressure, hydrogen formation, and primary and secondary flow rates. The Adaptive System Thermal-Hydraulics program was used in the simulation and event progression analysis. The results showed that the peak fuel surface temperature was kept below the licensing design limit. No observation of corium …

Threat Modeling Based On A Design Basis Threat For Nuclear Security, Abu Zafor Mohammad Salahuddin, Altab Hossain, Mohammad Shawkat Akbar

International Journal of Nuclear Security

Identification of the design basis threat (DBT) of a nuclear facility is an important factor of overall safety, for which the operator is mainly responsible per the guidelines of the International Atomic Energy Agency. As threat levels increase especially threats beyond the DBT-the responsibility of the state also increases. In recent years, only a few studies on nuclear security and DBTs have comprehensively detailed the full spectrum of nuclear facilities in a nation. Thus, this paper presents the correlation between an actual threat and the DBT. The objectives of the study are to assist in establishing physical protection system (PPS) …

Multilayer Shielding Design And Analysis Of Optimal Thickness For The Storage Of Highly Radioactive Sources Concerning Environmental Safety, Md. Mahfuzul Haque Rafi, Asma Ul Husna, Abdus Sattar Mollah

International Journal of Nuclear Security

As a kind of radiological protection, multilayer shielding is superior to a single-layer shield in terms of blocking off radiation. This study examined a multilayer shielding strategy to protect employees from potentially harmful gamma radiation from highly radioactive sources such as ⁶⁰Co. This paper presents a novel strategy for cost-effective and environmentally safe radiation protection by aligning expensive and heavy materials such as W and Pb to improve their effectiveness and limit exposure below the occupational dose. The largely unpublished set of final exposure rates for the W–Pb–Fe combination was calculated by the numerical interpolation method in MATLAB software. …

Insen 2023 Yearly Updates, Walid Metwally, Matteo Gerlini, Cristen Ford, João Claudio Batista Fiel J.C.B.F., Dr. Alpana Goel

International Journal of Nuclear Security

The International Nuclear Security Education Network (INSEN) is the primary international network for nuclear security educational initiatives. INSEN plays a central role in fostering collaboration and knowledge-sharing among nuclear security education experts worldwide. In the wake of the global pandemic, INSEN remained committed to strengthening nuclear security education and resumed in-person activities. The International Atomic Energy Agency (IAEA) confirmed its continued dedication and support to the network’s mission and presented new activities aimed at elevating global nuclear security efforts.

Throughout the year and during the annual and leadership meetings, working groups showcased their vibrant work and presented innovative ideas, invigorating …

A Case Study Assessing The Integration Of Nuclear Safety And Security In Facilities Using A Monte Carlo Simulation Aided Analytical Hierarchy Process, Theodore A. Thomas, Shraddha Rane, Jason Timothy Harris

International Journal of Nuclear Security

Nuclear safety and security are essential in all operations using nuclear and radioactive materials. Even though both elements are important, the evolution of these programs has not developed at the same rate. As such, their integration has been met with challenges. This study analyzed the potential for synergy across different criteria and settings when integrating nuclear safety and security. The criteria included eight points where overlap could be identified between nuclear safety and security. Three work settings—industrial, medical, and research—were evaluated. Responses were collected from nine individuals who worked with nuclear materials in various capacities and different nuclear work settings. …