scholarly journals Nuclear Power Plants Pre-operational Radiological Monitoring Mapping for the Coastal Boarders and Islands of the United Arab Emirates (UAE)

2021 ◽  
Vol 19 ◽  
pp. 31-39
Author(s):  
Ali S. Almeqbali ◽  
George Karani ◽  
Sayed A El-Mongy

In the light of the peaceful nuclear power plants (NPPs) project of the United Arab Emirates (UAE), the operation license has been issued and the first unit is being in commercial operation. This work deals mainly with radiological surveillance of the coastal boarder and some Islands of UAE as a baseline reference natural and artificial radioactivity mapping. Ultra-sensitive hyper pure Germanium (HpGe) detector was used to carry out the non-destructive gamma measurements. The area of study was divided into; Abu Dhabi region, northern emirates and islands. About 85 soils, shore sediment and water samples were collected based on the scientific sampling mechanism. The samples were analyzed for X-ray diffraction mineralogy (XRD). The radioactivity in Bq/kg of the natural 238U(226Ra), 232Th and 40K were calculated for all the collected samples. The artificial 137Cs was also observed in very low activity. The hazard indices were also calculated and found to be less than the recommended international and regional limits. The correlations between the measured radioisotopes were also depicted. The results were compared, presented and given in 3D histograms.

Author(s):  
Deok Hyun Lee ◽  
Do Haeng Hur ◽  
Myung Sik Choi ◽  
Kyung Mo Kim ◽  
Jung Ho Han ◽  
...  

Occurrences of a stress corrosion cracking in the steam generator tubes of operating nuclear power plants are closely related to the residual stress existing in the local region of a geometric change, that is, expansion transition, u-bend, ding, dent, bulge, etc. Therefore, information on the location, type and quantitative size of a geometric anomaly existing in a tube is a prerequisite to the activity of a non destructive inspection for an alert detection of an earlier crack and the prediction of a further crack evolution [1].


Author(s):  
Tae Kyo Kang ◽  
Won Ho Jo ◽  
Yeon Ho Cho ◽  
Sang Gyoon Chang ◽  
Dae Hee Lee

The reactor vessel head region consists of a number of components and systems including reactor vessel head, CEDMs with their cables, cooling air system with ducts and fans, missile shield, seismic supports, head lift rig and cable supports. Prior to refueling operation, those components must be dismantled separately, and moved to the designated storage area. It was a very complicated and time consuming process. As a result, the integrated head assembly (IHA) was introduced to simplify those disassembling procedures, reduce refueling outage period, and improve safety in the containment building as those components are combined into a single system. To reduce refueling outage duration and radiation exposures to the workers by integrating the complicated reactor head region structures, KEPCO E&C has developed the IHA concept in the Korean Next Generation Reactor (KNGR) project [1]. The first application was implemented for the Optimized Power Reactor 1000 (OPR1000) at Shin-Kori units 1&2 and Shin-Wolsong units 1&2. With the past experience, the IHA was upgraded to be applied to the Advanced Power Reactor 1400 (APR1400). The design was patented in Korea [2], China, EU and the USA as modular reactor head area assembly. The IHA was applied for APR1400 nuclear power plants at Shin-Kori and Shin-Hanul, Korea. The design was also supplied to Barakah Nuclear Power Plants in the United Arab Emirates. This paper presents the design features and a variety of analysis which have been used for the APR1400 IHA.


Atomic Energy ◽  
2012 ◽  
Vol 113 (1) ◽  
pp. 57-63
Author(s):  
Yu. G. Dragunov ◽  
B. P. Strelkov ◽  
A. A. Arefyev ◽  
A. S. Mokrousov ◽  
N. G. Roshchin

Author(s):  
Inge Uytdenhouwen ◽  
Rachid Chaouadi

Abstract Worldwide there are more than 449 nuclear power plants (NPPs) in operation among which 329 reactors are older than 25 years and 94 will be operating for more than 40 years in 2020. Lifetime extensions are requested up to 50–60 years and sometimes even up to 80 years of operation for many existing NPPs. Long-term operation (LTO) of existing NPPs has therefore been accepted in many countries as a strategic objective to ensure supply of electricity for the coming decades. Within this strategy, the European Commission launched the NOMAD project, among others, through the Horizon-2020 programme. The reactor pressure vessels (RPVs) cannot be tested destructively in a direct way, neither can it be replaced. An indirect way is the use of Charpy samples from the so-called surveillance programs. The general strategy on the long term should focus on the ability to perform direct non-destructive evaluation (NDE) of the embrittlement of the vessel. NDE can be used to confirm that the data obtained by surveillance programs are being representative of the real state of the vessel for LTO. Moreover, a generic concern of large nuclear components such as the reactor vessel is the possible material heterogeneity such as macro-segregated regions which could eventually be located in the component but not in the baseline material used as surveillance material. Local non-destructive material inspection and comparison to reference materials in similar irradiation conditions would lead to a better assessment of the properties of the materials at any location of the vessel. The objective of NOMAD is to develop a tool that is capable of non-destructively evaluate the embrittlement of the vessel wall. The final system should be capable of inspecting the microstructure of the materials through the cladding. The tool that will be developed, will use existing and proven nondestructive testing techniques (NDT) with optimized and adjusted sensors. A combination of several techniques based on micro-magnetic, electrical and ultrasonic methods are investigated. Within NOMAD, they are calibrated and validated on a set of existing and newly irradiated samples consisting out of the most common RPV steels from Eastern and Western design, such as 22NiMoCr37, 18MND5, A533-B, A508 Cl.2, A508 Cl.3 and 15kH2NMFA. For the first time, a systematic study on a well-characterized set of samples that correlates the microstructure, mechanical properties, neutron irradiation conditions and non-destructive properties will be carried out. It will not only extend the existing database, but will include issues such as reliability, and uncertainty of the techniques as well as on material heterogeneity. The focus is laid on unbroken Charpy samples and large blocks with and without cladding to “simulate” the actual RPV inspection scenario. This paper gives an overview of the present status of the NOMAD project with focus on the outcome in WP1. The first preliminary NDE results from 6 set-ups and 28 parameters were compared with DBTT results from Charpy impact tests. They are very promising. Final results and detailed analysis will however only be available at the end of the project.


2021 ◽  
pp. 20-26
Author(s):  
V. M. Ushakov

Topical aspects of non-destructive testing (NDT) of equipment and pipelines of power units of nuclear power plants (NPP) are considered. Non-destructive testing is an integral part of the entire life cycle of a nuclear power plant. Briefly analyzed documentation and types of non-destructive testing at the stage of manufacturing equipment and pipelines. Power of ultrasonic testing of welded joints of pipelines with a thickness of 2 to 6 mm. The main points of drawing up technological maps of non-destructive testing are noted. A brief analysis of the application of non-destructive testing in accordance with the requirements of the regulatory documents of the Russian Federation and the safety standards of the International Atomic Energy Agency is provided. It is shown that in recent years there has been a tendency to expand the role of NDTs from the classical approach of detecting and assessing defects to the use of NDTs in the study of metal degradation and ageing processes during the operation of NPP equipment and pipelines.


2020 ◽  
pp. 6-18
Author(s):  
V. M. Ushakov ◽  
S. G. Evtushenko ◽  
A. D. Zhukov ◽  
A. S. Yurechko

The paper presents some approaches and methods for assessing and evaluation of different properties of equipment and pipelines metal of nuclear power plants during an operation such as a stress-strain state, a temperature and electrochemical effects. A problem statement for ageing management is considered for such metal properties of the heat – bearing agents. For this purpose, an observation of literature is provided for non – destructive testing (NDT) methods that have a correlation to a degradation factor defined by certain properties. There is has been made a case to apply NDT methods as a promising tool for an estimation and evaluation of degradation factor for a metal of potentially hazardous equipment. For this purpose there are proposed some rational and efficient solutions likes of acoustic methods based on structural – reverberation noise analysis, electromagnetic methods based on a coercive field strength deviation and electrical methods based on principles of potentiometry.


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