Published 2000 | Version v1
Miscellaneous Metadata-only

Brittle fracture resistance assessment of modern NPP materials

Creators

  • 1. OAO Izhorskie Zavody, Sankt-Peterburg (Russian Federation)
  • 2. TsNII KM Prometej, Sankt-Peterburg (Russian Federation)

Description

A comparison is made for various parameters of resistance to brittle fracture for reactor vessel steels Cr-(Ni)-Mo-V in the form of forgings and plates - 15Kh(2-3)NMFA-A and 15Kh(2-3)MFA-A. The chemical composition of the steels studied is presented. The steels are different in harmful impurity elements of S and P, alloying degree and carbon equivalent. Mechanical properties and parameters of brittle fracture resistance of the steels are given. It is shown that the system of alloying, the blank thickness and the structure of the steel result not only in the essential difference in strength level but also in ductile-brittle transition temperatures. Thick-walled steel 15Kh3NMFA-A semiproducts are established to have rather high values of stress intensity factor in the temperature range of nuclear reactor vessel operation

Abstract (Russian)

Выполнено сопоставление различных характеристик сопротивления хрупкому разрушению для корпусных реакторных сталей Cr-(Ni)-Mo-V в виде поковок и плит - 15Х(2-3)НМФА-А и 15Х(2-3)МФА-А. Представлен химический состав исследованных сталей. Они отличаются содержанием вредных примесных элементов S and P, степенью легирования и величиной углеродного эквивалента. Приведены их механические свойства и характеристики сопротивления хрупкому разрушению. Показано, что в связи с различной системой легирования, толщиной заготовки и структурой исследуемые стали существенно отличаются не только по уровню прочности, но и по температурам вязко-хрупкого перехода. Для толстостенных заготовок стали 15Х3НМФА-А установлены достаточно высокие значения коэффициента интенсивности напряжений в температурном диапазоне эксплуатации корпусов атомных реакторов
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)
Оценка сопротивления хрупкому разрушению современных материалов AEhU

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. 159-169
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
33004627
Subject category
S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CHEMICAL COMPOSITION; CRACKS; DUCTILE-BRITTLE TRANSITIONS; LOW ALLOY STEELS; MECHANICAL PROPERTIES; MICROSTRUCTURE; PRESSURE VESSELS; STRESS INTENSITY FACTORS; TEMPERATURE DEPENDENCE; TRANSITION TEMPERATURE
Descriptors DEC
ALLOYS; CARBON ADDITIONS; CONTAINERS; IRON ALLOYS; IRON BASE ALLOYS; PHYSICAL PROPERTIES; STEELS; THERMODYNAMIC PROPERTIES; TRANSITION ELEMENT ALLOYS

Optional Information

Notes
6 refs., 5 figs., 2 tabs. Imprint:Trudy shestoj mezhdunarodnoj konferentsii. Problemy materialovedeniya pri proektirovanii, izgotovlenii i ehkspluatatsii oborudovaniya AEhS. Tom 2