Published 1996 | Version v1
Book Metadata-only

State of fuel elements in BN-600 reactor fuel assembly 917137489 when reaching maximal damaging dose of 93.7 dpa

Creators

Description

A complex of post-irradiated studies was accomplished for BN-600 reactor fuel cans of steel ChS-68. The studies were carried out by methods of profilometry, metallography short-term mechanical tests after irradiation up to damaging dose of 93.7 dpa. High volumetric changes, zero plasticity, corrosion defects testify to the fact that further operation of the steel under conditions of BN-600 reactor up to damaging doses more than 91-93 dpa is inadmissible

Abstract (Russian)

Проведен комплекс послереакторных исследований оболочек твэлов реактора БН-600, изготовленных из стали ЧС-68. Исследования проводили методами профилометрии, металлографии, кратковременных механических испытаний после облучения до повреждающей дозы 93,7 сна. Высокие объемные изменения, нулевая пластичность, коррозионное повреждение свидетельствуют о недопустимости дальнейшей эксплуатации этой стали в условиях реактора БН-600 до повреждающих доз более 91-93 сна
Part of:
Collection of reports of the 4. Inter-industry conference on reactor materials. Volume 3. Steels and alloys for various purpose nuclear reactors

Additional details

Additional titles

Original title (Russian)
Состояние твэлов TVS 917137489 реактора BN-600 после достижения максимальной повреждающей дозы 93,7 сна

Publishing Information

Publisher
GNTs RF NIIAR
Imprint Place
Dimitrovgrad (Russian Federation)
ISBN
5-85165-169-5
Imprint Title
Collection of reports of the 4. Inter-industry conference on reactor materials. Volume 3. Steels and alloys for various purpose nuclear reactors
Imprint Pagination
362 p.
Journal Page Range
p. 137-147

Conference

Title
4. Inter-industry conference on reactor materials
Original Conference Title
4. Mezhotraslevaya konferentsiya po reaktornomu materialovedeniyu
Dates
15-19 May 1995
Place
Dimitrovgrad (Russian Federation)

INIS

Country of Publication
Russian Federation
Country of Input or Organization
Russian Federation
INIS RN
32056859
Subject category
S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BELOYARSK-3 REACTOR; CHROMIUM-NICKEL-MOLYBDENUM STEELS; CORROSION; FRACTURES; FUEL CANS; PHYSICAL RADIATION EFFECTS; PLASTICITY; RADIATION DOSES; SERVICE LIFE
Descriptors DEC
ALLOYS; BREEDER REACTORS; CARBON ADDITIONS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; CHROMIUM STEELS; CHROMIUM-MOLYBDENUM STEELS; CHROMIUM-NICKEL STEELS; DOSES; EPITHERMAL REACTORS; FAILURES; FAST REACTORS; FBR TYPE REACTORS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; LIFETIME; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; MECHANICAL PROPERTIES; MOLYBDENUM ALLOYS; NICKEL ALLOYS; POWER REACTORS; RADIATION EFFECTS; REACTORS; SODIUM COOLED REACTORS; STAINLESS STEELS; STEELS; TRANSITION ELEMENT ALLOYS

Optional Information

Notes
6 figs., 2 tabs. Imprint:Sbornik dokladov 4. Mezhotraslevoj konferentsii po reaktornomu materialovedeniyu. Tom 3. Stali i splavy dlya yadernykh reaktorov razlichnogo naznacheniya