RU94040397A - Fuel rod, boiling water nuclear reactor with these fuel rods and nuclear power plant based on such type of nuclear reactor using - Google Patents

Fuel rod, boiling water nuclear reactor with these fuel rods and nuclear power plant based on such type of nuclear reactor using

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Publication number
RU94040397A
RU94040397A RU94040397/25A RU94040397A RU94040397A RU 94040397 A RU94040397 A RU 94040397A RU 94040397/25 A RU94040397/25 A RU 94040397/25A RU 94040397 A RU94040397 A RU 94040397A RU 94040397 A RU94040397 A RU 94040397A
Authority
RU
Russia
Prior art keywords
gas
nuclear
reactor
fuel
fuel rods
Prior art date
Application number
RU94040397/25A
Other languages
Russian (ru)
Other versions
RU2118001C1 (en
Inventor
Н.П. Колчев
Original Assignee
Н.П. Колчев
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 Н.П. Колчев filed Critical Н.П. Колчев
Priority to RU94040397A priority Critical patent/RU2118001C1/en
Publication of RU94040397A publication Critical patent/RU94040397A/en
Application granted granted Critical
Publication of RU2118001C1 publication Critical patent/RU2118001C1/en

Links

Classifications

    • Y—GENERAL 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
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y—GENERAL 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
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Landscapes

  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Engine Equipment That Uses Special Cycles (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

FIELD: nuclear power energy plant engineering. SUBSTANCE: fuel rod has envelope made like parallelepiped, which grate sides have height and width more than 600 times exceed same parameters of little sides. Besides, bigger sides are made wave-shaped, and theirs external surfaces are covered by layer of nuclear fuel. Fuel rods are installed one parallel to another with separations between them in nuclear reactor body and they are jointed from above and from below by bridgings. There are two separate hermetically spaces inside reactor body, which one is filled by water and it includes fuel rods free space, water cooling area and gas area between fuel rods composing gas circulation loop. Plant has pressure leveler equalizers made like pressure-tight vessels connected with reactor water pipe line and heat gas-carrier pipe lines. For gas transfer from gas circulation loop to tank gas compressor is used. EFFECT: higher efficiency and reliability of nuclear power plant.

Claims (1)

Изобретение относится к ядерной технике. Предложен тепловыделяющий элемент, оболочка которого имеет форму параллелепипеда, открытого сверху и снизу, большие грани которого имеют высоту и ширину, не менее чем в 600 раз превосходящие ширину малых граней. На наружной поверхности больших граней нанесен слой ядерного топлива. Большие грани имеют волнистую форму. Тепловыделяющие элементы установлены в ядерном реакторе параллельно друг другу с промежутками, соединенными сверху и снизу перекрытиями. Внутри реактора образованы два герметично отделенных друг от друга пространства: водяное, включающее пространства внутри тепловыделяющих элементов и входящее в состав водяного контура, и газовое, включающее промежутки между тепловыделяющими элементами и входящее в состав газового контура. Установка имеет в своем составе выравниватели давления, представляющие собой герметичные сосуды, соединенные с трубопроводом, подводящим воду к реактору, и трубопроводам, подводящим к реактору газовый теплоноситель. Имеется также компрессор, предназначенный для перекачивания газа из газового контура в емкости. Часть газа после реактора направляется на газовую турбину, вращающую циркуляционную газодувку. Предлагаемое изобретение повышает эффективность и надежность ядерной энергетической установки.The invention relates to nuclear technology. A heat-generating element is proposed, the shell of which has the shape of a parallelepiped, open at the top and bottom, large faces of which have a height and width not less than 600 times the width of small faces. A layer of nuclear fuel is deposited on the outer surface of large faces. Large faces have a wavy shape. The fuel elements are installed in the nuclear reactor parallel to each other with gaps connected from above and below by ceilings. Inside the reactor, two hermetically separated spaces are formed: water, including the spaces inside the fuel elements and included in the water circuit, and gas, including the gaps between the fuel elements and included in the gas circuit. The installation incorporates pressure equalizers, which are sealed vessels connected to a pipeline supplying water to the reactor, and pipelines supplying a gas coolant to the reactor. There is also a compressor designed to pump gas from the gas circuit into the tank. Part of the gas after the reactor is directed to a gas turbine that rotates the circulating gas blower. The present invention improves the efficiency and reliability of a nuclear power plant.
RU94040397A 1994-10-19 1994-10-19 Boiling reactor and nuclear power plant using it RU2118001C1 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
RU94040397A RU2118001C1 (en) 1994-10-19 1994-10-19 Boiling reactor and nuclear power plant using it

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
RU94040397A RU2118001C1 (en) 1994-10-19 1994-10-19 Boiling reactor and nuclear power plant using it

Publications (2)

Publication Number Publication Date
RU94040397A true RU94040397A (en) 1997-03-10
RU2118001C1 RU2118001C1 (en) 1998-08-20

Family

ID=20162221

Family Applications (1)

Application Number Title Priority Date Filing Date
RU94040397A RU2118001C1 (en) 1994-10-19 1994-10-19 Boiling reactor and nuclear power plant using it

Country Status (1)

Country Link
RU (1) RU2118001C1 (en)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
RU2493482C2 (en) * 2011-10-28 2013-09-20 Юрий Михайлович Красильников Steam generation plant of single-circuit nuclear power plant

Also Published As

Publication number Publication date
RU2118001C1 (en) 1998-08-20

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