ASSESSMENT OF THE SYSTEM CHARACTERISTICS OF A REACTOR WITH SUPERCRITICAL COOLANT PARAMETERS FOR VARIOUS FUEL CYCLES

Author:

Lapin A1,Bobryashov A1,Blandinsky V1,Bobrov E1

Affiliation:

1. National Research Center “Kurchatov Institute”

Abstract

Nowadays nuclear energy operates in an open fuel cycle. One of the most important directions in the development of nuclear energy is the closure of the nuclear fuel cycle. The solution to this problem is possible with the use of fast neutron reactors. To achieve this goal, the possibility of using a reactor with a fast-resonance neutron spectrum cooled by supercritical water (SCWR) was considered. The SCWR reactor can be effectively used in a closed nuclear fuel cycle, since it makes it possible to use spent fuel and dump uranium with a small amount of plutonium added. The layout options of the core with a change in the size of the core and reproduction zones are considered. The possibility of placing reproduction zones from various materials inside the active zone was evaluated. Based on the studies, an acceptable version of the core is selected in terms of system characteristics. For the considered arrangement of the reactor core, the possibility of shorting the uranium-plutonium and uranium-thorium fuel cycles has been investigated. The system characteristics of the reactor installation were studied for the following fuel load options: 1. Loading MOX fuel into the core, depleted uranium in the lateral zone of reproduction. 2. Loading of uranium-thorium fuel into the core and side screens. The results of the assessments of the system characteristics of the reactor are considered in the article.

Publisher

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

Reference8 articles.

1. Workshop on Advanced Nuclear Reactor Safety Issues and Research Needs. Proc. NEA/OECD Workshop. Paris, France, 2002. , Workshop on Advanced Nuclear Reactor Safety Issues and Research Needs. Proc. NEA/OECD Workshop. Paris, France, 2002.

2. Вознесенский В.А., Левина И.К., Духовенский А.С., Силин В.А. Энергетический реактор ВВЭР 1000 СКД повышенной безопасности. М.: ИАЭ им. И. В. Курчатова, 1989, гл. 2.1.2-2.1.3. С. 52-79. , Voznesenskiy V.A., Levina I.K., Duhovenskiy A.S., Silin V.A. Energeticheskiy reaktor VVER 1000 SKD povyshennoy bezopasnosti. M.: IAE im. I. V. Kurchatova, 1989, gl. 2.1.2-2.1.3. S. 52-79.

3. Орлов В.В., Слесарев И.С., Калафати Д.Д., Гришанин Е.И., Зверков Ю.А., Субботин С.А., Щепетина Т.Д., Кузнецов В.В., Седов А.А., Стукалов В.А., Фальковский Л.Н., Фомиченко П.А. Атомная станция с пароводоохлаждаемым энергетическим реактором повышенной безопасности. Теплоэнергетика, 1990, № 8, с. 27-31. , Orlov V.V., Slesarev I.S., Kalafati D.D., Grishanin E.I., Zverkov Yu.A., Subbotin S.A., Schepetina T.D., Kuznecov V.V., Sedov A.A., Stukalov V.A., Fal'kovskiy L.N., Fomichenko P.A. Atomnaya stanciya s parovodoohlazhdaemym energeticheskim reaktorom povyshennoy bezopasnosti. Teploenergetika, 1990, № 8, s. 27-31.

4. Субботин С.А., Чибиняев А.В., Седов А.А., Семченков Ю.М. Перспективы и проблемы использования в реакторах легководного теплоносителя сверхкритического давления для повышения эффективности ядерного топливного цикла. Вопросы атомной науки и техники. Сер. Физика ядерных реакторов, 2010, вып. 1, с. 3-12. , Subbotin S.A., Chibinyaev A.V., Sedov A.A., Semchenkov Yu.M. Perspektivy i problemy ispol'zovaniya v reaktorah legkovodnogo teplonositelya sverhkriticheskogo davleniya dlya povysheniya effektivnosti yadernogo toplivnogo cikla. Voprosy atomnoy nauki i tehniki. Ser. Fizika yadernyh reaktorov, 2010, vyp. 1, s. 3-12.

5. Чибиняев А.В., Алексеев П.Н., Теплов П.С., Фролова М.В. Нейтронно-физические характеристики двухконтурного энергетического реактора с закритическими параметрами пара. Труды 7 Межд. научно-техн. конф. «Обеспечение безопасности АЭС с ВВЭР». Подольск, 2011, с. 36-37. , Chibinyaev A.V., Alekseev P.N., Teplov P.S., Frolova M.V. Neytronno-fizicheskie harakteristiki dvuhkonturnogo energeticheskogo reaktora s zakriticheskimi parametrami para. Trudy 7 Mezhd. nauchno-tehn. konf. «Obespechenie bezopasnosti AES s VVER». Podol'sk, 2011, s. 36-37.

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