Alternative Method of Non-Destructive Testing for Nuclear Power Plant
- 1. National Research Nuclear University MEPhI 115409, Kashirskoe shosse, 31 Moscow (Russian Federation)
- 2. Volgodonsk Engineering Technical Institute-MEPhI 73/94 Lenin St., Volgodonsk, Rostov region, 347360 (Russian Federation)
- 3. Jordan Atomic Energy Commission Amman, Jordan, P. O. Box 70, Amman 11934 (Jordan)
Description
This study presents the results of electrophysical non-destructive testing of collectors welded joints to the body of steam generators PGV 1000Mof the reactor WWER-1000. The studied steam generators located in the Resource Сenter of National Research Nuclear University MEPhI at the site of reactors construction factory "Atommash" in Volgodonskcity-Russia. The primary loop collector was welded to the body of steam generators PGV 1000Mand the technical condition of welded joints was investigated by electrophysical non-destructive testing (EPhT). In steam generatorsmay appear corrosion and cracks due to corrosive environment and effect of stresses however,EPhTcan detect early stages of cracks. The study highlights the theoretical part of electrophysical diagnostics and control method, using modern mathematical signals analysis, and issues related to the practical implementation of EPhT in the factory. The novel alternative method of non-destructive testing can be used in diagnostic oil and gas pipelines, elements of complex technical structures and industrial equipment. It can be used in many industries where it is necessary to process control of the entire structure or its individual parts under operating conditions. Based on control results, potentiograms were constructed for various structural levels of the diagnostic signal. The results of controlled welded joints in steam generators showed their satisfactory condition.
Availability note (English)
Available from https://www.epj-conferences.org/articles/epjconf/pdf/2021/01/epjconf_physor2020_11002.pdf; https://doaj.org/article/a5d0f0d60be24546a7070b45396aa845Additional details
Identifiers
Publishing Information
- Journal Title
- EPJ. Web of Conferences
- Journal Volume
- 247
- Journal Page Range
- vp.
- ISSN
- 2100-014X
Conference
- Title
- International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future
- Acronym
- PHYSOR2020
- Dates
- 28 Mar - 2 Apr 2020
- Place
- Cambridge (United Kingdom)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 53087707
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S46: INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CORROSION; IMPLEMENTATION; NONDESTRUCTIVE TESTING; NUCLEAR POWER PLANTS; PIPELINES; PRIMARY COOLANT CIRCUITS; PROCESS CONTROL; SIGNALS; STEAM GENERATORS; WELDED JOINTS; WWER TYPE REACTORS
- Descriptors DEC
- BOILERS; CHEMICAL REACTIONS; CONTROL; COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; JOINTS; MATERIALS TESTING; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; TESTING; THERMAL POWER PLANTS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS