Investigation and development of the technology for automatic welding of pipes of P91 (X10CrMoVNb9-1) steel

Khodakov, V. D.; Abrosin, A.A.; Bazanov, M.A.; Praliyev, D.A.; Khodakov, D.V.; Gudenko, A. S.

doi:10.1080/09507116.2014.998431

Cited by 1 publication

(3 citation statements)

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“…According to [48], the degradation mechanisms for the flaws in the dissimilar material welds at WWERs are usually a combination of corrosion on the carbon steel side and stress-corrosion-cracking interdendritic character. The factors determining the cracking, i.e., the stresses, the material, and the environment have been thoroughly investigated, e.g., [48][49][50][51][52][53][54][55][56][57][58]. Cases of DMW degradations have been found and repaired at Dukovany NPP and Kola NPP [48,57,58].…”

Section: Steam Generatormentioning

confidence: 99%

“…The factors determining the cracking, i.e., the stresses, the material, and the environment have been thoroughly investigated, e.g., [48][49][50][51][52][53][54][55][56][57][58]. Cases of DMW degradations have been found and repaired at Dukovany NPP and Kola NPP [48,57,58]. The approach of ASME, 2013 Section XI was applied to evaluate allowable flaw sizes in the DMW connecting the austenitic stainless-steel primary pipe to the K22 ferritic steel body of the steam generator [52,53].…”

Section: Steam Generatormentioning

confidence: 99%

“…The approach of ASME, 2013 Section XI was applied to evaluate allowable flaw sizes in the DMW connecting the austenitic stainless-steel primary pipe to the K22 ferritic steel body of the steam generator [52,53]. A thorough nondestructive examination indicates the performance of these newly repaired DMWs [58]. From the point of view of SG operability for up to 60-70 years, the DMW issue is manageable since verified methods are available for monitoring the degradation and repair.…”

Section: Steam Generatormentioning

confidence: 99%

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Feasibility of Safe Operation of WWER-440-Type Nuclear Power Plants for Up to 60–70 Years

Katona

Biro²,

Ratkai³

2023

Energies

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Most WWER-440 reactors are operated over the planned operational lifetime of 30 years. Now, the owners/operators are preparing for the second phase of extending the operation. The paper presents an overview of the most important aspects of ageing of the main components of the WWER-440-type reactors based on the operational and ageing management experiences and primary research efforts supporting the operation. The paper aims to demonstrate that the expectations for the operability of these reactors for up to 60–70 years are realistic. The scope of the review is limited to the ageing of the reactor pressure vessel, vessel internals, and steam generator, which are the lifetime-limiting components besides the containment structure. Some of the corrective actions, improvements of in-service inspections, maintenance, and ageing management are also considered in the paper. It is shown that the selection of materials and unavoidable material degradation processes do not limit the operation of the WWER-440 reactors for up to 60–70 years under the established operational environment and ageing management practice.

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