Published 2001 | Version v1
Book Metadata-only

Low temperature swelling of austenitic stainless steels

Creators

  • 1. Gosudarstvennyj Nauchnyj Tsentr RF Fiziko-Ehnergeticheskij Inst. im. A.I. Lejpunskogo, Obninsk (Russian Federation)
  • 2. Tikhookeanskaya Severo-Zapadnaya Natsional'naya Lab., Richland (United States)

Description

The investigation results are presented for swelling of austenitic steels 12Kh18N9T, 0Kh16N15M3BR and 00Kh16N15M3B irradiated at temperatures below 340 deg C in BN-350 and BOR-60 fast reactors as well as in one of water-water reactors. Based on electron microscopical examination the following conclusions are drawn: in steel 12Kh18N9T irradiated in BN-350 reactor at damaging doses of 26.3 to 55.4 dpa vacancy voids are observed in the temperature range of 302-316 deg C; in steel OKh16N15M3BR after irradiation in BOR-60 reactor the voids defined by electron microscopy are revealed at irradiation temperatures exceeding 314 deg C and at irradiation temperatures exceeding deg C and at damaging doses more than 4.3 dpa; the irradiation of steel 00Kh16N15M3B in a water-water reactor results in void formation at irradiation temperatures above 310 deg C and damaging doses of 2.1-6.1 dpa. A mean void diameter varies from 23 to 173 A depending on irradiation temperatures and doses

Abstract (Russian)

Приведены результаты исследования распухания аустенитных сталей 12Х18Н9, 0Х16Н15М3БР и 00Х16Н15М3Б после облучения при температурах ниже 340 град С в быстрых реакторах БН-350 и БОР-60, а также в одном из водо-водяных реакторов. На основании электронномикроскопических исследований облученных образцов сделаны следующие выводы: в стали 12Х18Н9Т, облученной в реакторе БН-350 при повреждающих дозах от 26.3 до 55.4 сна наблюдаются вакансионные поры в температурном диапазоне 302-316 град С; в стали 0Х16Н15М3БР после облучения в реакторе БОР-60 разрешимые в электронный микроскоп поры обнаружены при температурах облучения, превышающих 314 град С при повреждающих дозах более 4.3 сна; облучение стали 00Х16Н15М3Б в водо-водяном реакторе приводит к образованию пор при температурах облучения, превышающих 310 град С и повреждающих дозах 2.1-6.1 сна. В зависимости от температуры и дозы облучения средний диаметр пор меняется от 23 до 173 А
Part of:
The collection of reports of 6. Russian conference on reactor material science. Vol. 3. P. 1. Structural materials of nuclear reactors

Additional details

Additional titles

Original title (Russian)
Низкотемпературное распухание аустенитных нержавеющих сталей

Publishing Information

Publisher
GNTs RF NIIAR
Imprint Place
Dimitrovgrad (Russian Federation)
ISBN
5-85165-651-4
Imprint Title
Collection of reports of 6. Russian conference on reactor material science. Vol. 3. P. 1. Structural materials of nuclear reactors
Imprint Pagination
334 p.
Journal Page Range
p. 24-35

Conference

Title
6. Russian conference on reactor material science
Original Conference Title
Shestaya Rossijskaya konferentsiya po reaktornomu materialovedeniyu
Dates
11-15 Sep 2000
Place
Dimitrovgrad (Russian Federation)

INIS

Country of Publication
Russian Federation
Country of Input or Organization
Russian Federation
INIS RN
33057311
Subject category
S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BN-350 REACTOR; PHYSICAL RADIATION EFFECTS; RADIATION DOSES; STEEL-CR16NI15MO3NB; STEEL-CR18NI9TI; SWELLING; TEMPERATURE RANGE 0400-1000 K; VACANCIES
Descriptors DEC
ALLOYS; AUSTENITIC STEELS; BREEDER REACTORS; CHROMIUM ALLOYS; CHROMIUM STEELS; CHROMIUM-MOLYBDENUM STEELS; CHROMIUM-NICKEL STEELS; CHROMIUM-NICKEL-MOLYBDENUM STEELS; CORROSION RESISTANT ALLOYS; CRYSTAL DEFECTS; CRYSTAL STRUCTURE; DEFORMATION; DESALINATION REACTORS; DOSES; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; MATERIALS; MOLYBDENUM ALLOYS; NICKEL ALLOYS; NIOBIUM ADDITIONS; NIOBIUM ALLOYS; POINT DEFECTS; RADIATION EFFECTS; REACTORS; SODIUM COOLED REACTORS; STAINLESS STEELS; STEELS; TEMPERATURE RANGE; TITANIUM ADDITIONS; TITANIUM ALLOYS; TRANSITION ELEMENT ALLOYS

Optional Information

Notes
3 figs., 7 tabs. Imprint:Sbornik dokladov Shestoj Rossijskoj konferentsii po reaktornomu materialovedeniyu. Tom 3. Chast' 1. Konstruktsionnye materialy yadernykh reaktorov