Abstract
The essential service water system (ESWS) in nuclear power plants circulates the water that cools fan coolers, cooling water heat exchangers, and condensers and other components before dissipating the heat into the environment. Because this includes cooling the systems that remove decay heat from both the primary system and the spent fuel rod cooling ponds, the ESWS is a safety-critical system. In locations without a large body of water in which to dissipate the heat, water is recirculated via a cooling tower. Cooling towers fall into two main categories: Natural draft and Mechanical draft. Since, the mechanical draft cooling towers are much more widely used; the focus is on them in this work to measure its performance. Therefore; the present work addresses the thermal acceptance test for mechanical draft water cooling tower in order to determine its thermal capability in accordance with the cooling technology institute (CTI) code recommendations. Both the Characteristic Curve and the Performance Curve Methods are used. A detailed description of the test procedure according to the CTI ATC-105 test code is presented, and the test code is applied on the Egypt second research reactor (ETRR-2) cooling tower as a case study. All the instruments used in the reactor plant are calibrated prior the test and the measured data is collected at regular intervals according to the code recommendations. The test result shows a tower capability of about 105 % and so the tower is thermally accepted.
Nomenclature
- a
-
Area of transfer surface per unit of tower volume
- BHP
-
Break horse power
- C w
-
Water specific heat
- G
-
Air flow rate
- h 1
-
Enthalpy of inlet air
- h 2
-
Enthalpy of exit air
- h w
-
Enthalpy of the film
- h a
-
Enthalpy of the bulk air
- KaV/L
-
Tower characteristic
- L
-
Water flow rate
- L/G
-
Mass flow ratio
- Q
-
Tower capability
- T
-
Temperature
- T 1
-
Cold water temperature
- T 2
-
Hot water temperature
- V
-
Effective cooling tower volume
-
Research ethics: Not applicable.
-
Informed consent: Not applicable.
-
Author contributions: El-Morshedy: 70% and Shouman: 30%.
-
Use of Large Language Models, AI and Machine Learning Tools: Not applicable.
-
Conflict of interest: The authors state no conflict of interest.
-
Research funding: None declared.
-
Data availability: Not applicable.
References
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© 2024 Walter de Gruyter GmbH, Berlin/Boston
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- A new approach to determine abnormality of radioactive discharges from pressurized water reactors and to derive abnormality indicators correlated with a specific causal event
- A critical analysis of the role of artificial intelligence and machine learning in enhancing nuclear waste management
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Artikel in diesem Heft
- Frontmatter
- Comprehensive review of surface contamination in nuclear waste waters: identification, quantification, and mitigation strategies
- Methodology of probabilistic safety assessment for transportation of radioactive material
- A new approach to determine abnormality of radioactive discharges from pressurized water reactors and to derive abnormality indicators correlated with a specific causal event
- A critical analysis of the role of artificial intelligence and machine learning in enhancing nuclear waste management
- Design study of gas-cooled fast reactor with natural uranium as fuel employing modified CANDLE shuffling strategy in the axial direction
- Synthesis, structural transformation and magnetic properties of the Nd(III)-doped Fe3−xNd x O4 (0 ≤ x ≤ 0.9): an analogue for actinicles immobilization
- Examination of the use of thorium-based fuel for burning minor actinides in European sodium cooled fast reactor
- Solitary wave form of reaction rate in graphite diffusive medium using different neutron absorbers
- Evaluation of the unavailability of the primary circuit of Triga SSR reactor, importance factors and risk criteria for its components
- Thermal-hydraulic simulation of loss of flow accident for WWR-S research reactor
- A quick parameter configuration tool for SCHISM’s ocean transport simulation of radioactive materials
- Main heat transport system configuration influence on steam drum level control and safety for a pressure tube type boiling water reactor with multiple interconnected loops
- Testing the thermal performance of water cooling towers
- Design a robust intelligent power controller for pressurized water reactor using particle swarm optimization algorithm
- Calendar of events