Published 2000 | Version v1
Miscellaneous Metadata-only

Erosion - corrosion wear of steam lines and pipelines of the secondary circuit of NPPs with WWER under conditions of long term operation

Creators

  • 1. EhNITs VNIIAEhS, Ehlektrogorsk (Russian Federation)
  • 2. VNIIAEhS, Moscow (Russian Federation)

Description

The results of erosion - corrosion wear (ECW) analysis are given for steam and condensate feed pipes of a WWER NP secondary coolant circuit. Basic ECW parameters are presented to be applied to main steam pipes, drain pipes, main condensate pipes and others at the Zaporozhe-2 reactor. It is shown that the most thinning is observed in a stretched part of main condensate pipelines, main steam pipes hold the second place and steam separator and drain pipes occupy the third one. Straight portions are thinned in main condensate and feed water pipes as well as in steam separator and drain pipes. As for main steam pipelines, the straight portions remain practically unthinned

Abstract (Russian)

Приведены результаты анализа эрозионно - коррозионного износа (ЭКИ) трубопроводов парового и конденсатно - питательного тракта второго контура энергоблоков АЭС с ВВЭР. Представлены основные показатели ЭКИ трубопроводов свежего пара, дренажных, основного конденсата и других на энергоблоке 2 Запорожской АЭС. Показано, что наибольшие утонения фиксируются на растянутой части трубопроводов основного конденсата, на втором месте находятся трубопроводы свежего пара и на третьем месте - трубопроводы сепарата и дренажные трубопроводы. Прямые участки утоняются на трубопроводах основного коеденсата и питательной воды, а также сепарата и дренажных. На трубопроводах свежего пара прямые участки практически не утоняются
Part of:
Proceedings of the sixth international conference on material issues in design, manufacturing and operation of nuclear power plants equipment. Volume 2

Additional details

Additional titles

Original title (Russian)
Эрозионно - коррозионный износ паропроводов и трубопроводов второго контура в условиях длительной эксплуатации на AEhS с VVEhR

Publishing Information

Imprint Place
St. Petersburg (Russian Federation)
Imprint Title
Proceedings of the sixth international conference on material issues in design, manufacturing and operation of nuclear power plants equipment. Volume 2
Imprint Pagination
402 p.
Journal Page Range
p. 289-297
Report number
INIS-RU--453

Conference

Title
6. international conference on material issues in design, manufacturing and operation of nuclear power plants equipment
Original Conference Title
Shestaya mezhdunarodnaya konferentsiya: Problemy materialovedeniya pri proektirovanii, izgotovlenii i ehkspluatatsii oborudovaniya AEhS
Dates
19-23 Jun 2000
Place
St. Petersburg (Russian Federation)

INIS

Country of Publication
Russian Federation
Country of Input or Organization
Russian Federation
INIS RN
33004639
Subject category
S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CORROSION; EROSION; NUCLEAR POWER PLANTS; NUMERICAL SOLUTION; PIPELINES; SECONDARY COOLANT CIRCUITS; STEAM LINES; WATER; WEAR; ZAPOROZHE-2 REACTOR
Descriptors DEC
CHEMICAL REACTIONS; COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; HYDROGEN COMPOUNDS; NUCLEAR FACILITIES; OXYGEN COMPOUNDS; POWER PLANTS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS

Optional Information

Notes
2 refs., 4 tabs. Imprint:Trudy shestoj mezhdunarodnoj konferentsii. Problemy materialovedeniya pri proektirovanii, izgotovlenii i ehkspluatatsii oborudovaniya AEhS. Tom 2