The Determination of Shock Accelerations on a Small Nuclear Power Plant Structural Elements When Falling to the Surface

Due to high radioactivity and significant content of medium- and long-lived radionuclides, different operations with spent nuclear fuels (e.g., handling, transportation, and storage) shall be accompanied by suitable radiation protections. On the other hand, determination of radioactive source specification is the initial step for any radiation protection design. In this study, radioactive source specification of the spent fuels of Bushehr nuclear power plant, which is a VVER-1000 type pressurized water reactor, was determined. For the depletion and decay calculations, ORIGEN code was utilized. The results are presented for burnups of 30 to 49 GWd/MTHM and different cooling times up to 100 years. According to these results, total activity of a spent fuel assembly with initial enrichment of 3.92%, burnup of 49 GWd/MTHM, and cooling time of 3 years is 1.92 × 1016 Bq. The results can be utilized specifically in transportation/storage cask design for spent fuel management of Bushehr nuclear power plant.

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Determination of the safety rods (SA, SB) for optimized power reactor 1000 using the Core simulator OPR1000

Science and Technology Development Journal - Natural Sciences ◽

10.32508/stdjns.v1i6.627 ◽

2018 ◽

Vol 1 (6) ◽

pp. 177-184

Author(s):

Son An Nguyen ◽

Nguyen Trung Tran

Keyword(s):

Power Plant ◽

Nuclear Power Plant ◽

Nuclear Power ◽

Nuclear Reactor ◽

Boron Concentration ◽

Power Reactor ◽

Experimental Simulation ◽

The Core ◽

Operation Process

In order to operate a nuclear power plant, ensuring safety is the most important factor. The function of safety rods are to shut down the reactor in case of emergency. The purpose of this paper to show the result of research and determine the value of safety rods SA, SB. Determination of the Boron concentration corresponding to each group of safety rods of OPR1000 nuclear reactor ensures the safely in the whole operation process. Experimental simulation is carried out in the system simulating core reactor OP1R1000 (CoSi OPR1000). The expermental result corresponds with the theoretic calculated result of Sa and Sb with 1500 pcm, 4000 pcm. The concentrations of Boron appropriately are 134 ppm and 284 ppm, respectively.

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Thermal Performance Monitoring and Optimization in Dukovany NPP

Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues ◽

10.1115/icone22-30735 ◽

2014 ◽

Author(s):

Jiri Pliska ◽

Zdenek Machat ◽

Libor Veznik ◽

Jiri Smisek

Keyword(s):

Power Plant ◽

Nuclear Power Plant ◽

Thermal Performance ◽

Nuclear Power ◽

Performance Monitoring ◽

Accurate Determination ◽

Process Data ◽

Important Indicator ◽

Operation And Maintenance

Competition in the electricity market forces producers to achieve — in compliance with safety — efficiency of production as high as possible. This efficiency and heat rate is an important indicator of both the condition of the power plant equipment and the quality of power plant operation. To cope with these challenges, powerful methods are process data reconciliation, statistical data processing of large data sets and process simulation. These functions and methods can be used to obtain useful information about process quality and equipment and sensor health. The paper discusses practical experience from six years of using a thermal performance monitoring and optimization system in the Dukovany nuclear power plant. The system is integrated into the overall nuclear power plant process information system and data warehouse. The system provides information in near real time. The major benefit of the system lies in a deep view into equipment behaviour and process which ensures timely detection and identification of functionality degradation of process and equipment or sensor faults. The system also helps to find and use margins of equipment operation and the overall thermal cycle. Selected practical examples are used to demonstrate specific benefits of the system for operation and maintenance of the Dukovany nuclear power plant. There are examples of equipment fault detection and sensor degradation detection. The optimization function is explained with an example of cooling circuit optimization aimed to increase the delivery of electrical power into the grid. A detailed description of behaviour of the main components can be used for their performance evaluation and their repair planning. The benefit of more accurate determination of parameter values is reflected in more accurate determination of reactor thermal output. The conclusion of the paper provides an overall evaluation of system benefits for operation and maintenance of a nuclear power plant.

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