RU94015052A - Nuclear power plant - Google Patents

Nuclear power plant

Info

Publication number
RU94015052A
RU94015052A RU94015052/25A RU94015052A RU94015052A RU 94015052 A RU94015052 A RU 94015052A RU 94015052/25 A RU94015052/25 A RU 94015052/25A RU 94015052 A RU94015052 A RU 94015052A RU 94015052 A RU94015052 A RU 94015052A
Authority
RU
Russia
Prior art keywords
channels
fuel
rows
reactor
loops
Prior art date
Application number
RU94015052/25A
Other languages
Russian (ru)
Other versions
RU2075124C1 (en
Inventor
В.А. Иванов
Original Assignee
В.А. Иванов
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by В.А. Иванов filed Critical В.А. Иванов
Priority to RU9494015052A priority Critical patent/RU2075124C1/en
Publication of RU94015052A publication Critical patent/RU94015052A/en
Application granted granted Critical
Publication of RU2075124C1 publication Critical patent/RU2075124C1/en

Links

Classifications

    • 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
    • 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

Landscapes

  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

FIELD: nuclear power engineering. SUBSTANCE: nuclear power plant has nuclear reactor whose core incorporates alternating rows of channels set in parallel within each row and in rows abutting same row arranged so that angle between axes of adjacent channels in direction of coolant flow is 45 to 135 deg; it also has at least two coolant circuit loops; channels of at least one of mentioned rows are arranged horizontally. Effective cooling of fuel in dry channels of defective loops is attained due to the fact that channels of at least one row adjacent to mentioned row of horizontal channels are also arranged horizontally and these two rows have fuel channels communicating for coolant with different loops of reactor cooling circuit, respectively. Fuel in faulty channels and tubes of serviceable ones come in contact due to plastic strain of tubes of faulty channels and parts used for spacing fuel elements in fuel assemblies under mass of fuel in faulty channels. EFFECT: improved safety of power plant with pressure-tube reactor. 21 cl, 12 dwg

Claims (1)

Изобретение относится к атомной энергетики и позволяет повысить безопасность энергетической установки с канальным ядерным реактором. Сущность - ЯЗУ включает ядерный реактор, активная зона которого выполнена с чередованием рядов каналов, установленных параллельно в пределах ряда и в рядах, примыкающих к одному и тому же ряду, расположенных так, что угол между осями каналов смежных рядов в направлении движения теплоносителя составляет от 45 до 135o, и по крайней мере две петли контура охлаждения реактора, причем каналы одного из упомянутых рядов расположены горизонтально. Повышение безопасности ЯЗУ достигается путем увеличения эффективности охлаждения топлива в осушенных каналах аварийных петель за счет того, что каналы по крайней мере одного одного ряда, смежного с упомянутым рядом горизонтальных каналов, также расположены горизонтально, причем эти два ряда содержат каналы для топлива, подключенные по теплоносителю соответственно к разным петлям контура охлаждения реактора. Необходимый контакт топлива аварийных каналов и труб неаварийных каналов обеспечивается в результате пластической деформации труб аварийных каналов и элементов, используемых для дистанционирования твэлов в тепловыделяющих сборках, под тяжестью топлива, размещенного в аврийных каналах. Эффективность применения указанного технического решения с указанной целью обусловлена особенностью реактора предлагаемойй ЯЗУ, для самогашения цепной ядерной реакции, в которой достаточно обезвоживания даже одной из петель контура охлаждения реактора. 20 з.п.ф-лы, 12 ил.The invention relates to nuclear energy and can improve the safety of a power plant with a channel nuclear reactor. SUBSTANCE: nuclear reactor includes a nuclear reactor, the core of which is made with alternating rows of channels installed in parallel within a row and in rows adjacent to the same row, located so that the angle between the axes of the channels of adjacent rows in the direction of movement of the coolant is from 45 up to 135 o , and at least two loops of the reactor cooling circuit, the channels of one of the said rows are located horizontally. Improving the safety of the fuel supply system is achieved by increasing the cooling efficiency of the fuel in the drained channels of the emergency loops due to the fact that the channels of at least one row adjacent to the horizontal channels mentioned above are also horizontal, and these two rows contain fuel channels connected through the coolant respectively, to different loops of the reactor cooling loop. The necessary fuel contact of emergency channels and non-emergency channel pipes is ensured as a result of plastic deformation of emergency channel pipes and elements used for spacing fuel rods in fuel assemblies under the weight of the fuel placed in emergency channels. The effectiveness of the use of the indicated technical solution for the indicated purpose is due to the particularity of the reactor of the proposed NZU, for self-quenching of the nuclear chain reaction, in which even one of the loops of the reactor cooling loop is dehydrated. 20 C.p. f-ls, 12 ill.
RU9494015052A 1994-04-22 1994-04-22 Nuclear energy device RU2075124C1 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
RU9494015052A RU2075124C1 (en) 1994-04-22 1994-04-22 Nuclear energy device

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
RU9494015052A RU2075124C1 (en) 1994-04-22 1994-04-22 Nuclear energy device

Publications (2)

Publication Number Publication Date
RU94015052A true RU94015052A (en) 1996-06-10
RU2075124C1 RU2075124C1 (en) 1997-03-10

Family

ID=20155148

Family Applications (1)

Application Number Title Priority Date Filing Date
RU9494015052A RU2075124C1 (en) 1994-04-22 1994-04-22 Nuclear energy device

Country Status (1)

Country Link
RU (1) RU2075124C1 (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2010151178A3 (en) * 2009-06-25 2011-03-03 Lebedev Larion Aleksandrovich Nuclear reactor control method

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2010151178A3 (en) * 2009-06-25 2011-03-03 Lebedev Larion Aleksandrovich Nuclear reactor control method

Also Published As

Publication number Publication date
RU2075124C1 (en) 1997-03-10

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