Published 2000 | Version v1
Miscellaneous Metadata-only

The execution of the research programme of the post-operational control over the properties of the Russian icebreaker Lenin RPV materials and perspectives of the implementation of the results operating nuclear driven icebreakers assessment and increasing

Creators

  • 1. Inst. Reaktornykh Tekhnologij i Materialov Rossijskogo Nauchnogo Tsentra Kurchatovskij Inst., Moscow (Russian Federation)
  • 2. Opytnoe Konstruktorskoe Byuro Mashinostroeniya, Nizhnij Novgorod (Russian Federation)

Description

Reactor vessel materials of the Lenin nuclear ship (ns) after a 18 year operation are tested and studied. It is shown that it is beyond reason to change the procedure of standardized approach to estimation of reactor vessel lifetime under irradiation for nuclear steam-generating systems now in operation. The base metal of the Lenin ns reactor vessel is stated to be of high quality as by an initial value of critical temperature of embrittlement so by its radiation resistance. The weld metal has a reasonable radiation resistance, but its initial transition temperature (approximately 63 deg C) is inadequate. The study of radiation resistance parameters for reactor vessels having been in operation over 18 years should be continued

Abstract (Russian)

Проведены испытания и иследовано состояние материалов корпуса реактора а/л Ленин после 18 лет эксплуатации. Показано, что нет достаточных оснований для корректировки процедуры нормативного подхода к определению радиационного ресурса корпусов реакторов действующих атомных парапроизводящих установок. Установлено, что основной металл корпуса реактора а/л Ленин имеет высокое качество как по параметру исходного значения критической температуры хрупкости, так и по радиационной стойкости. Металл сварного шва имеет достаточную радиационную стойкость, но неудовлетворительную исходную критической температуры хрупкости (примерно 63 град С). Следует продолжать исследование параметров радиационной стойкости для корпусов реакторов, эксплуатирующихся более 18 лет
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)
Реализация программы послеэксплуатационного контроля состояния металла корпуса реактора N1 атомного ледокола Ленин и перспективы применения результатов для продления радиационного ресурса корпусов реакторов атомных ледоколов

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. 91-99
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
33004623
Subject category
S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
DUCTILE-BRITTLE TRANSITIONS; LENIN REACTOR; MATERIALS TESTING; NS LENIN; PHYSICAL RADIATION EFFECTS; PRESSURE VESSELS; SERVICE LIFE; STEELS; TRANSITION TEMPERATURE; WELDED JOINTS
Descriptors DEC
ALLOYS; CARBON ADDITIONS; CONTAINERS; ENRICHED URANIUM REACTORS; IRON ALLOYS; IRON BASE ALLOYS; JOINTS; LIFETIME; NUCLEAR SHIPS; PHYSICAL PROPERTIES; POWER REACTORS; PROPULSION REACTORS; PWR TYPE REACTORS; RADIATION EFFECTS; REACTORS; SHIP PROPULSION REACTORS; SHIPS; TESTING; THERMAL REACTORS; THERMODYNAMIC PROPERTIES; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
4 figs., 3tabs. Imprint:Trudy shestoj mezhdunarodnoj konferentsii. Problemy materialovedeniya pri proektirovanii, izgotovlenii i ehkspluatatsii oborudovaniya AEhS. Tom 2