SU449656A1 - Method for limiting the consequences of a nuclear power plant accident - Google Patents

Method for limiting the consequences of a nuclear power plant accident

Info

Publication number
SU449656A1
SU449656A1 SU1763708A SU1763708A SU449656A1 SU 449656 A1 SU449656 A1 SU 449656A1 SU 1763708 A SU1763708 A SU 1763708A SU 1763708 A SU1763708 A SU 1763708A SU 449656 A1 SU449656 A1 SU 449656A1
Authority
SU
USSR - Soviet Union
Prior art keywords
consequences
limiting
power plant
nuclear power
accident
Prior art date
Application number
SU1763708A
Other languages
Russian (ru)
Inventor
А.М. Букринский
Л.И. Турецкий
В.Н. Миронов
Original Assignee
Всесоюзный Дважды Ордена Трудового Красного Знамени Теплотехнический Научно-Исследовательский Институт Им.Ф.Э.Дзержинского
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
Priority to BE791572D priority Critical patent/BE791572A/en
Application filed by Всесоюзный Дважды Ордена Трудового Красного Знамени Теплотехнический Научно-Исследовательский Институт Им.Ф.Э.Дзержинского filed Critical Всесоюзный Дважды Ордена Трудового Красного Знамени Теплотехнический Научно-Исследовательский Институт Им.Ф.Э.Дзержинского
Priority to SU1763708A priority patent/SU449656A1/en
Priority to BG21912A priority patent/BG20737A1/xx
Priority to DD167016A priority patent/DD102848A1/xx
Priority to FR7242872A priority patent/FR2177700A1/en
Priority to RO197273029A priority patent/RO63470A/en
Priority to IT33148/72A priority patent/IT974734B/en
Priority to CS2325A priority patent/CS160475B1/cs
Application granted granted Critical
Publication of SU449656A1 publication Critical patent/SU449656A1/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
    • Y02E30/30—Nuclear fission reactors

Description

.54) СПОСОБ ОГРАНИЧЕНИЯ ПОСЛЕДСТВИЙ АВАРИИ НА АТОМНОЙ ЭЛЕКТРОСТАНЦИИ.54) METHOD FOR LIMITING THE CONSEQUENCES OF AN ACCIDENT AT A NUCLEAR POWER PLANT

Если помещение 2 первого контура рассчитано по пронности на наибольшее даЕление, например 1 кгс/см , то клапанна  системаIf the room 2 of the first circuit is designed for the permeability of the greatest day, for example 1 kgf / cm, then the valve system

4может быть настроена на срабатывание4can be configured to trigger

при давлении в отсеке 3 0,3-0,5 кгс/см , 5 При суммарном объеме помещени  2 и отсека 3 15000-20000 м и диаметре разорвавшегос  трубопровода 500-700 мм клапанна  система 4 срабатывает в первую секунду после аварии. При подаче воды из емкости юWith a pressure in the compartment 3 0.3-0.5 kgf / cm, 5 With a total volume of room 2 and compartment 3 15000-20000 m and a diameter of 500-700 mm of a ruptured pipeline, valve system 4 is activated in the first second after the accident. When water is supplied from the tank

5в первые секунды после аварии в количестве 20-30 давление в помещении 2 и отсеке 3 будет падать так быстро, что уже через 8-10 сек после аварии клапанна  система закроетс  и затем в помещении 15 2 и отсеке 3 установитс  давление ниже атмосферного . За 8-10 сек, в течение которых осуществл етс  выброс паровоздушной смеси за пределы аварийного помещени , из первого контура успевает вытечь больша  205 in the first seconds after the accident in the amount of 20-30, the pressure in room 2 and compartment 3 will fall so quickly that after 8-10 seconds after the accident the valve system closes and then in room 15 2 and compartment 3 the pressure will be below atmospheric. In 8–10 seconds, during which the vapor-air mixture is ejected outside the emergency room, a large amount of time has flowed out of the primary circuit.

часть теплоносител  и давление в контуре падает по сравнению с рабочим в 3-5 раз.part of the coolant and the pressure in the circuit decreases in comparison with the worker 3-5 times.

Claims (1)

Формула изобретени Invention Formula Способ ограничени  последствий аварии на атомной электростанции при разрыве главного трубопровода, предусматривающий снижение давлени  в помещении первого контура путем подачи хладагента дл  конденсадии паров, образующихс  при вскипании теплоносител , и выброс малоактивной паровоздущной смеси за пределы аварийного помещени , отличающийс  тем, что, с целью повышени  надежности защиты окружающей среды от радиоактивного загр знени , паровоздушную смесь направл ют к месту выброса через воздушное пространство емкостью не менее 20-30% от объема аварийного помещени ,A method for limiting the consequences of an accident at a nuclear power plant when the main pipeline is ruptured, which involves reducing the pressure in the primary circuit by supplying refrigerant for condensation of vapors formed during boiling up of the coolant and discharging the low-active air-vapor mixture outside the emergency room, characterized in protecting the environment from radioactive contamination, the vapor-air mixture is directed to the site of release through an air space of at least 20-30% m volume of placing an emergency,
SU1763708A 1972-03-30 1972-03-30 Method for limiting the consequences of a nuclear power plant accident SU449656A1 (en)

Priority Applications (8)

Application Number Priority Date Filing Date Title
BE791572D BE791572A (en) 1972-03-30 METHOD AND SYSTEM FOR LIMITING THE FOLLOW-UP OF A DAMAGE IN ATOMIC POWER PLANTS
SU1763708A SU449656A1 (en) 1972-03-30 1972-03-30 Method for limiting the consequences of a nuclear power plant accident
BG21912A BG20737A1 (en) 1972-03-30 1972-11-20
DD167016A DD102848A1 (en) 1972-03-30 1972-11-22
FR7242872A FR2177700A1 (en) 1972-03-30 1972-12-01 Nuclear power station damage control - with containment system for leaking coolant
RO197273029A RO63470A (en) 1972-03-30 1972-12-04 METHOD AND INSTALLATION FOR LIMITING TRACTORS OF DAMAGE TO NUCLEAR POWER PLANTS
IT33148/72A IT974734B (en) 1972-03-30 1972-12-19 PROCEDURE AND SYSTEM TO LIMIT THE CONSEQUENCES OF FAILURES IN ATOMIC POWER PLANTS MAINLY TO THE LOSS OF THE CALO RE VEHICLE FROM THE FIRST CIRCUIT
CS2325A CS160475B1 (en) 1972-03-30 1973-03-30

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
SU1763708A SU449656A1 (en) 1972-03-30 1972-03-30 Method for limiting the consequences of a nuclear power plant accident

Publications (1)

Publication Number Publication Date
SU449656A1 true SU449656A1 (en) 1977-01-25

Family

ID=20507856

Family Applications (1)

Application Number Title Priority Date Filing Date
SU1763708A SU449656A1 (en) 1972-03-30 1972-03-30 Method for limiting the consequences of a nuclear power plant accident

Country Status (1)

Country Link
SU (1) SU449656A1 (en)

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