Effect of neutron irradiation on response of reinforced concrete members for nuclear power plants

2016 ◽  
Vol 310 ◽  
pp. 15-26 ◽  
Author(s):  
Kyoungsoo Park ◽  
Hyung-Tae Kim ◽  
Tae-Hyun Kwon ◽  
Eunsoo Choi
2017 ◽  
Vol 82 (733) ◽  
pp. 433-440
Author(s):  
Hideyoshi WATANABE ◽  
Masahiko WATANABE ◽  
Hideo HIRAI ◽  
Kunihiko SATO ◽  
Tetsuo IMAOKA ◽  
...  

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.


Structures ◽  
2020 ◽  
Vol 27 ◽  
pp. 732-746
Author(s):  
Muhammad Sadiq ◽  
Wasim Khaliq ◽  
Muhammad Ilyas ◽  
Rao Arsalan Khushnood ◽  
Shaukat Ali Khan ◽  
...  

Author(s):  
Tomohiro Nishizawa ◽  
Takao Nishikawa ◽  
Katsuki Takiguchi ◽  
Hiroyuki Sugita ◽  
Yasuo Hijioka ◽  
...  

“Rules on Concrete Containment Vessels for Nuclear Power Plants” was first published in 2003. It was revised in 2011 and the latest Edition was published in 2015. Endorsement of this Code is expected in the very near future. There are two types of reactor containments: steel containment vessels (hereinafter referred to as “SCV”) and concrete containment vessels (hereinafter referred to as “CCV”). The former is addressed by Rules on Design and Construction for Nuclear Power Plants, and the latter by Rules on Concrete Containment Vessels for Nuclear Power Plants, including Reinforced Concrete Containment Vessel (hereinafter referred to as “RCCV”), Pre-stressed Concrete Containment Vessel (hereinafter referred to as “PCCV”), and hybrid containment vessels which are required further safety and reliability.


2021 ◽  
Vol 108 ◽  
pp. 35-44
Author(s):  
Jakub Holan ◽  
Petr Bíly ◽  
Radek Štefan

Nowadays, the safety of nuclear power plants is of increasing interest and importance. The main reasons for increased safety concerns are the recent major nuclear accident in Fukushima in 2011 and the overall tendency of environment protection. One of the possible ways of increasing the safety of nuclear power plants is the underground placement of all potentially dangerous systems under ground as the overlying soil or rock layer would act as a "earth" containment which would reduce the probability of ground level release following primary and secondary containment failure. Moreover, partial or total underground placement of nuclear power plant would reduce its visibility, and thus, public concerns would also be reduced. However, many design, operational, and economic disadvantages are linked with the underground placement of nuclear power plants. The aim of this paper is to provide state-of-the-art review of existing underground nuclear reactors, conceptual designs of underground nuclear reactors, and related literature, which can later be used for the design of a underground reinforced concrete containment building.


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