RU2019136276A - Iron Oxide Portland Cement for Nuclear Reactor Melt Trap - Google Patents

Iron Oxide Portland Cement for Nuclear Reactor Melt Trap Download PDF

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Publication number
RU2019136276A
RU2019136276A RU2019136276A RU2019136276A RU2019136276A RU 2019136276 A RU2019136276 A RU 2019136276A RU 2019136276 A RU2019136276 A RU 2019136276A RU 2019136276 A RU2019136276 A RU 2019136276A RU 2019136276 A RU2019136276 A RU 2019136276A
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RU
Russia
Prior art keywords
iron oxide
cement
portland cement
nuclear reactor
components
Prior art date
Application number
RU2019136276A
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Russian (ru)
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RU2019136276A3 (en
RU2754136C2 (en
Inventor
Александр Стальевич Сидоров
Юрий Петрович Удалов
Николай Фёдорович Фёдоров
Вячеслав Иванович Зотов
Евгений Николаевич Засыпалов
Роман Валерьевич Титов
Original Assignee
Акционерное общество "Тяжмаш"
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Application filed by Акционерное общество "Тяжмаш" filed Critical Акционерное общество "Тяжмаш"
Priority to RU2019136276A priority Critical patent/RU2754136C2/en
Publication of RU2019136276A publication Critical patent/RU2019136276A/en
Publication of RU2019136276A3 publication Critical patent/RU2019136276A3/ru
Application granted granted Critical
Publication of RU2754136C2 publication Critical patent/RU2754136C2/en

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Classifications

    • CCHEMISTRY; METALLURGY
    • C04CEMENTS; CONCRETE; ARTIFICIAL STONE; CERAMICS; REFRACTORIES
    • C04BLIME, MAGNESIA; SLAG; CEMENTS; COMPOSITIONS THEREOF, e.g. MORTARS, CONCRETE OR LIKE BUILDING MATERIALS; ARTIFICIAL STONE; CERAMICS; REFRACTORIES; TREATMENT OF NATURAL STONE
    • C04B7/00Hydraulic cements
    • C04B7/36Manufacture of hydraulic cements in general
    • C04B7/48Clinker treatment
    • C04B7/52Grinding ; After-treatment of ground cement
    • CCHEMISTRY; METALLURGY
    • C04CEMENTS; CONCRETE; ARTIFICIAL STONE; CERAMICS; REFRACTORIES
    • C04BLIME, MAGNESIA; SLAG; CEMENTS; COMPOSITIONS THEREOF, e.g. MORTARS, CONCRETE OR LIKE BUILDING MATERIALS; ARTIFICIAL STONE; CERAMICS; REFRACTORIES; TREATMENT OF NATURAL STONE
    • C04B7/00Hydraulic cements
    • C04B7/36Manufacture of hydraulic cements in general
    • C04B7/48Clinker treatment
    • C04B7/52Grinding ; After-treatment of ground cement
    • C04B7/522After-treatment of ground cement
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C9/00Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
    • G21C9/016Core catchers
    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Claims (6)

1. Состав железооксидного портланцемента для ловушки расплава ядерного реактора изготавливаемый путем сухого помола компонентов, отличающийся тем, что в качестве вяжущего вещества используется готовый цемент класса не ниже 42,5, в качестве активной минеральной добавки оксид железа III, а в качестве поверхностно активного вещества - суперпластификатор С-3 при следующем соотношении компонентов, мас.%:1. The composition of iron oxide portlane cement for trapping the melt of a nuclear reactor made by dry grinding of components, characterized in that ready-made cement of class not lower than 42.5 is used as a binder, iron oxide III is used as an active mineral additive, and as a surfactant - superplasticizer C-3 with the following ratio of components, wt%: портландцементPortland cement 30-50 30-50 оксид железа IIIiron oxide III 50-6550-65 суперпластификаторsuperplasticizer 0,8-1,80.8-1.8
2. Железооксидный портландцемент по п. 1, отличающийся тем, что компоненты измельчаются и смешиваются в мельнице интенсивного помола до размера поверхности порошка по Блейну в интервале 7000-10000 см2/г.2. Iron oxide Portland cement according to claim 1, characterized in that the components are ground and mixed in an intensive grinding mill to a powder surface size according to Blaine in the range of 7000-10000 cm 2 / g. 3. Способ по п. 2, отличающийся тем, что для получения из железооксидного портландцемента теста нормальной пластичности водоцементное отношение находится в интервале 0,16-0,25.3. A method according to claim 2, characterized in that for obtaining a test of normal plasticity from iron oxide Portland cement, the water-cement ratio is in the range of 0.16-0.25. 4. Способ по п. 3, отличающийся тем, что цементный камень после 28 суток твердения имеет кажущуюся плотность 2,40-2,85 г/см3.4. The method according to claim 3, characterized in that the cement stone after 28 days of hardening has an apparent density of 2.40-2.85 g / cm 3 . 5. Способ по п. 3, отличающийся тем, что потери при прокаливании цементного камня при температуре 700° равны 4,7-6,1 мас.% (потери физически и химически связанной воды), а при температуре 1000° равны 5,7-8,9 мас.% (общие потери за счет удаления летучих веществ - воды и углекислого газа).5. The method according to claim 3, characterized in that the losses during calcination of the cement stone at a temperature of 700 ° are 4.7-6.1 wt.% (Losses of physically and chemically bound water), and at a temperature of 1000 ° are equal to 5.7 -8.9 wt.% (Total losses due to the removal of volatile substances - water and carbon dioxide).
RU2019136276A 2019-11-11 2019-11-11 Iron-oxide portland cement for core catcher of nuclear reactor RU2754136C2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
RU2019136276A RU2754136C2 (en) 2019-11-11 2019-11-11 Iron-oxide portland cement for core catcher of nuclear reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
RU2019136276A RU2754136C2 (en) 2019-11-11 2019-11-11 Iron-oxide portland cement for core catcher of nuclear reactor

Publications (3)

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RU2019136276A true RU2019136276A (en) 2021-05-11
RU2019136276A3 RU2019136276A3 (en) 2021-05-11
RU2754136C2 RU2754136C2 (en) 2021-08-30

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Family Applications (1)

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RU2019136276A RU2754136C2 (en) 2019-11-11 2019-11-11 Iron-oxide portland cement for core catcher of nuclear reactor

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Family Cites Families (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
RU2096362C1 (en) * 1995-11-30 1997-11-20 Акционерное общество закрытого типа "Акционерная компания ПОЛИМОД в области модификаторов бетона" Binding agent
RU2182137C1 (en) * 2000-12-22 2002-05-10 Кузьмина Вера Павловна Dry mix and method of its preparation
RU2215340C2 (en) * 2002-01-08 2003-10-27 Санкт-Петербургский государственный технологический институт (технический университет) Cement for nuclear reactor molten core catcher
EA003961B1 (en) * 2003-02-13 2003-10-30 Санкт-Петербургский государственный технологический институт (технический университет) Ceramic material for catching a melt of active zone of nuclear rector
RU2605693C1 (en) * 2015-12-17 2016-12-27 Федеральное государственное бюджетное учреждение науки Физико-технический институт им. А.Ф. Иоффе Российской академии наук Oxide material of nuclear reactor core melt trap
RU2656270C1 (en) * 2017-04-17 2018-06-04 Вадим Григорьевич Хозин Low water demand cement and method of its manufacturing

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RU2019136276A3 (en) 2021-05-11
RU2754136C2 (en) 2021-08-30

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