THE SYNERGETIC OF FUEL ELEMENT-Reference-Cited by-同舟云学术

THE SYNERGETIC OF FUEL ELEMENT

Published:2019-09-26 Issue:3 Volume:2019 Page:261-272
ISSN:2414-1038
Container-title:PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. SERIES: NUCLEAR AND REACTOR CONSTANTS
language:en
Short-container-title:

Author:

Orlova E¹

Affiliation:

1. Obninsk Institute for Nuclear Power Engineering

Abstract

The fuel element is the complex system consisting of fuel, a sublayer, a cladding, protective coatings on a surface of a cladding and contacting to the cooler and material of a contour in general. The synergetic (self-coherence) of interaction of elements of this system has to be provided both concerning high heat conductivity of fuel element, and concerning corrosion compatibility. Use of a liquid metal sublayer (LMS) instead of gas, allows significantly (by hundreds of degrees) to reduce temperature in the center of fuel that increases safety at UTOP accidents (uncontrollable increase in power) at ULOF (loss of an expense of the cooler). Gap thickness when using LMS (unlike helium) can be significantly increased that will practically not affect thermal characteristics of fuel element, but will allow to distance considerably time of approach of direct contact of fuel with a cladding, having increased thereby depth of burning out of heavy atoms and having increased cost efficiency and competitiveness of fast reactors extension of the fuel elements resource. These principles when using heat-conducting nuclear fuel are especially effective (metal, nitride, carbide) and the lead heat carrier. Synergetic reasonable corrosion compatibility of a cladding of fuel element with LMS is confirmed with numerous settlement pilot studies by means of formation and self-curing of accidental damages of a protective coating of nitride of zirconium on the internal surface of steel in LMS of eutectic structure on the basis of lead with magnesium and zirconium. When using nitride fuel heat-conducting LMS with anticorrosive properties the resource of fuel element is limited not by swelling of fuel any more, and the dose damaging a cladding.

Publisher

Institute for Physics and Power Engineering (IPPE, Inc.)

Reference24 articles.

1. Adamov Е.О., Orlov V.V., Smirnov V.S. Progress in lead cooled fast reactor design. Proc. Intern. Conf. on Design and Safety of Advanced Nuclear Power Plants. Tokyo, Japan, 1992, vol. 2, pp. 1-4. , Adamov E.O., Orlov V.V., Smirnov V.S. Progress in lead cooled fast reactor design. Proc. Intern. Conf. on Design and Safety of Advanced Nuclear Power Plants. Tokyo, Japan, 1992, vol. 2, pp. 1-4.

2. Орлов В.В., Пикалов А.А., Сила-Новицкий А.Г. и др. Экспериментальный петлевой канал в реакторе БОР-60 для испытаний твэлов реакторов БРЕСТ. Труды международной конференции «Тяжелые жидкометаллические теплоносители в ядерных технологиях» ТЖМТ-98. Обнинск, 1999, с. 521-528. , Orlov V.V., Pikalov A.A., Sila-Novickiy A.G. i dr. Eksperimental'nyy petlevoy kanal v reaktore BOR-60 dlya ispytaniy tvelov reaktorov BREST. Trudy mezhdunarodnoy konferencii «Tyazhelye zhidkometallicheskie teplonositeli v yadernyh tehnologiyah» TZhMT-98. Obninsk, 1999, s. 521-528.

3. Кордюков А.Г., Леонов В.Н., Пикалов А.А. и др. Испытания макетов твэлов реактора Брест-ОД-300 в автономном свинцово-охлаждаемом канале БОР-60. Атомная энергия, 2004, т. 97, вып. 2, с. 131-138. , Kordyukov A.G., Leonov V.N., Pikalov A.A. i dr. Ispytaniya maketov tvelov reaktora Brest-OD-300 v avtonomnom svincovo-ohlazhdaemom kanale BOR-60. Atomnaya energiya, 2004, t. 97, vyp. 2, s. 131-138.

4. Беляева А.В., Крюков Ф.Н., Никитин О.Н. и др. Основные результаты исследований уран-плутониевого нитридного топлива после облучения в реакторе БОР-60. Труды Международной научно-технической конференции «Инновационные продукты и технологии ядерной энергетики». Москва, 2012, с. 223-228. , Belyaeva A.V., Kryukov F.N., Nikitin O.N. i dr. Osnovnye rezul'taty issledovaniy uran-plutonievogo nitridnogo topliva posle oblucheniya v reaktore BOR-60. Trudy Mezhdunarodnoy nauchno-tehnicheskoy konferencii «Innovacionnye produkty i tehnologii yadernoy energetiki». Moskva, 2012, s. 223-228.

5. Орлов В.В., Орлова Е.А., Цикунов В.С. и др. Формирование защитных нитридных покрытий на поверхности сталей. Препринт НИКИЭТ № ЕТ-08/77. Москва, 2008. , Orlov V.V., Orlova E.A., Cikunov V.S. i dr. Formirovanie zaschitnyh nitridnyh pokrytiy na poverhnosti staley. Preprint NIKIET № ET-08/77. Moskva, 2008.