@sharjah.ac.ae
Mechanical and Nuclear Engineering
University of Sharjah
PhD in Nuclear and Mechanical Engineering
Nuclear Energy and Engineering, Energy Engineering and Power Technology
Scopus Publications
Scholar Citations
Scholar h-index
Scholar i10-index
Min Jeong Park, Yong Gyun Shin, Belal Almomani, and Yoon-Suk Chang
Elsevier BV
Ammar Alkhalidi, Belal Almomani, A.G. Olabi, and Hussam Jouhara
Elsevier BV
Belal Almomani, Ammar Alkhalidi, A.G. Olabi, and Hussam Jouhara
Elsevier BV
Omarelfarouq Elgack, Belal Almomani, Junaidi Syarif, Mohamed Elazab, Mohammad Irshaid, and Mohammad Al-Shabi
Elsevier BV
Belal Almomani, Tae-Yong Kim, and Yoon-Suk Chang
Elsevier BV
Belal Almomani, Junaidi Syarif, and Yoon-Suk Chang
Springer Science and Business Media LLC
Belal Almomani, Ahmad Ababneh, and Muhammad Zubair
Informa UK Limited
Abstract After the Three Mile Island Unit 2 accident, regulatory bodies were concerned about the safety measures in design and operation corresponding to the operator’s decisions and procedures for handling such off-normal transients. Several recommendations were proposed to analyze transients and accidents, improve and revise emergency operating procedures (EOPs), and conduct functional training. In this work, procedural paths were systematically studied to identify the problems in the diagnosis associated with a pilot-operated relief valve (PORV)–break loss-of-coolant accident (LOCA) as well as to suggest new indications for improving the EOPs. Operational parameters during PORV-break LOCA and pipeline-break small-break LOCA were analyzed using a generic pressurized water reactor simulator to compare and justify the symptoms between these two events. It was found that suggesting further indications mainly in the reactor cooling system and containment symptoms may improve the diagnosis of a PORV-break LOCA from the pipeline-break small-break LOCA. This paper presents a practical approach to evaluating diagnostic procedures to better understand operator recovery actions corresponding to reactor system response in dealing with a PORV-break LOCA.
Bassam A. Khuwaileh, Fatima E. Alzaabi, Belal Almomani, and Muataz Ali
Informa UK Limited
ABSTRACT The shortage of fresh water supply is a serious concern in the United Arab Emirates (UAE); such aspects make it nearly impossible to sustain the generation of potable water by strategies other than seawater desalination. With rising concerns over utilizing conventional energy technologies, nuclear desalination is seen as an effective option. The objective of this study is to evaluate the potential cost of seawater nuclear desalination for the UAE in two meteorological seasons of summer and winter. Three desalination techniques including reverse osmosis (RO), multi-effect distillation with thermal vapor compressors (MED-TVC), and a hybrid combination of MED-TVC+RO coupled to Barakah Nuclear Power Plant (BNPP) are assessed using IAEA’s DEEP-5 code. A sensitivity analysis is also conducted including a parametric variation in the interest rate, discount rate, and specific unit cost of the desalination plant. The seasonal study indicates that water costs increased in the winter, relative to summer with the MED-TVC being the highest in cost, followed by MED-TVC+RO, and RO. The power cost is found to be the only parameter affected by the interest and discount rates and, thus, the RO is the most economically competitive technology with further advantages in terms of safety aspects.
Belal Almomani, SaeHanSol Kang, Yoon-Suk Chang, and Jae-soo Noh
Springer Science and Business Media LLC
Belal Almomani, Tae-Yong Kim, and Yoon-Suk Chang
Elsevier BV
Ji-Hoon Kang, Belal Almomani, and Yoon-Suk Chang
ASME International
Abstract Accurate estimation of elastic-plastic fracture mechanics (EPFM) parameters for a crack in nuclear pipes was considered as an important factor for leak-before-break design and evaluation. Yet few EPFM studies have been made to predict the crack opening displacement and J-integral of dissimilar metal welded pipes, which consist of two-layered materials (TLMs), due to the difficulty of complicate analysis encompassing both through-wall crack and internal surface crack in radial and circumferential directions. In this study, a series of finite element analyses to determine the typical EPFM parameters were carried out considering idealized complex-cracked pipes with TLMs. The analyses were elaborated through applying three loading conditions of axial tension, bending moment, and internal pressure. Both J-integral and crack opening displacement values were calculated by assuming two kinds of equivalent materials based on weighted average concepts as well as two different materials. The proposed equivalent schemes can be utilized in not only improving the expansion to existing solutions but also in more accurate detailed leak-before-break assessment of complex cracked nuclear piping with TLMs.
Belal Almomani and Yoon-Suk Chang
Elsevier BV
Belal Almomani, Seyeon Kim, Dongchan Jang, and Sanghoon Lee
Elsevier BV
Belal Almomani, Dongchan Jang, and Sanghoon Lee
Elsevier BV
Mirae Yun, Robby Christian, Bo Gyung Kim, Belal Almomani, Jaehyun Ham, Sanghoon Lee, and Hyun Gook Kang
Elsevier BV
Belal Almomani, Dongchan Jang, Sanghoon Lee, and Hyun Gook Kang
Elsevier BV
Belal Almomani, Sanghoon Lee, Dongchan Jang, and Hyun Gook Kang
Elsevier BV
Belal Almomani, Sanghoon Lee, and Hyun Gook Kang
Elsevier BV