ES307183A1 - Perfeccionamientos en instalaciones de reactores nucleares sometidos a presiën - Google Patents

Perfeccionamientos en instalaciones de reactores nucleares sometidos a presiën

Info

Publication number
ES307183A1
ES307183A1 ES0307183A ES307183A ES307183A1 ES 307183 A1 ES307183 A1 ES 307183A1 ES 0307183 A ES0307183 A ES 0307183A ES 307183 A ES307183 A ES 307183A ES 307183 A1 ES307183 A1 ES 307183A1
Authority
ES
Spain
Prior art keywords
coolant
escape
pressure
steam
reactor
Prior art date
Legal status (The legal status 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 status listed.)
Expired
Application number
ES0307183A
Other languages
English (en)
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
UK Atomic Energy Authority
Original Assignee
UK Atomic Energy Authority
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 UK Atomic Energy Authority filed Critical UK Atomic Energy Authority
Publication of ES307183A1 publication Critical patent/ES307183A1/es
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C1/00Reactor types
    • G21C1/04Thermal reactors ; Epithermal reactors
    • G21C1/06Heterogeneous reactors, i.e. in which fuel and moderator are separated
    • G21C1/14Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor
    • G21C1/16Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor
    • G21C1/18Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor coolant being pressurised
    • G21C1/20Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor coolant being pressurised moderator being liquid, e.g. pressure-tube reactor
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C13/00Pressure vessels; Containment vessels; Containment in general
    • G21C13/10Means for preventing contamination in the event of leakage, e.g. double wall
    • 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
    • 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

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Lift Valve (AREA)
ES0307183A 1963-12-16 1964-12-16 Perfeccionamientos en instalaciones de reactores nucleares sometidos a presiën Expired ES307183A1 (es)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB49660/63A GB1081673A (en) 1963-12-16 1963-12-16 Improvements in or relating to pressurised nuclear reactor installations

Publications (1)

Publication Number Publication Date
ES307183A1 true ES307183A1 (es) 1965-05-16

Family

ID=10453109

Family Applications (1)

Application Number Title Priority Date Filing Date
ES0307183A Expired ES307183A1 (es) 1963-12-16 1964-12-16 Perfeccionamientos en instalaciones de reactores nucleares sometidos a presiën

Country Status (4)

Country Link
US (1) US3321374A (es)
DE (2) DE1227577B (es)
ES (1) ES307183A1 (es)
GB (2) GB1081673A (es)

Families Citing this family (9)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB1112213A (en) * 1966-04-28 1968-05-01 Atomic Energy Authority Uk Nuclear reactors
GB1472477A (en) * 1974-05-10 1977-05-04 Nuclear Power Co Ltd Nuclear reactor installations
SU537389A1 (ru) * 1974-06-05 1976-11-30 Всесоюзный Дважды Ордена Трудового Красного Знамени Теплотехнический Научно-Исследовательский Институт Им.Ф.Э.Дзержинского Система ограничени последствий аварии на атомных электростанци х
US4213824A (en) * 1977-06-23 1980-07-22 The Babcock & Wilcox Company Nuclear steam system containment
SE428611B (sv) * 1979-12-17 1983-07-11 Asea Atom Ab Nodkylningsanordning vid kokarvattenreaktor
FR2487563A1 (fr) * 1980-07-25 1982-01-29 Framatome Sa Procede et dispositif de refroidissement de secours d'un reacteur nucleaire
DE3037468A1 (de) * 1980-10-03 1982-05-06 Kernforschungsanlage Jülich GmbH, 5170 Jülich Vorrichtung zum schutz des sicherheitsbehaelters eines kernkraftwerkes gegen ueberdruckversagen
JP5627245B2 (ja) * 2010-02-09 2014-11-19 三菱重工業株式会社 原子力施設の建屋の基礎版および原子力施設
GB201009998D0 (en) 2010-06-15 2010-07-21 Bg Res Cell disruption

Family Cites Families (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB862627A (en) * 1958-03-14 1961-03-15 Gen Motors Corp Improved variable-speed power transmission mechanism for motor vehicles and the like
NL113562C (es) * 1959-02-24
BE630686A (es) * 1962-04-06 1900-01-01
NL297053A (es) * 1962-08-23 1900-01-01
GB1042643A (en) * 1963-01-24 1966-09-14 Asea Ab Pressure-absorbing means for nuclear reactor stations
GB972901A (en) * 1965-08-24 1964-10-21 Atomic Energy Authority Uk Steam generating nuclear reactor systems
US3258403A (en) * 1963-05-24 1966-06-28 Westinghouse Electric Corp Nuclear reactor containment system

Also Published As

Publication number Publication date
GB1081673A (en) 1967-08-31
GB1100625A (en) 1968-01-24
US3321374A (en) 1967-05-23
DE1227577B (de) 1966-10-27
DE1300174B (de) 1969-07-31

Similar Documents

Publication Publication Date Title
US3431168A (en) Reactor cooling system
US10529457B2 (en) Defense in depth safety paradigm for nuclear reactor
US20200194135A1 (en) Depressurisation valve
DE1764504A1 (de) Reaktorkuehlsystem
ES307183A1 (es) Perfeccionamientos en instalaciones de reactores nucleares sometidos a presiën
GB972901A (en) Steam generating nuclear reactor systems
GB1237390A (en) Nuclear reactor installations
Collier et al. The Accident at Three Mile Island
Lee et al. Effects of the operating strategies of filtered containment venting system on Cesium-137 releases during severe accidents
Bao et al. Simulation of BWR Mark I Station Black-Out accident using GOTHIC: an initial demonstration
Ullah et al. Steam Generator Tube Rupture Accident at a NPP and Exploration of Mitigation Strategies for Its Consequence
Thulu et al. An Investigation on the Possible Radioactive Contamination of Environment due to a Large Steam Line Break, Containment Rupture and Station Blackout in ABWR
Chen et al. MELCOR Analysis of Severe Accident Risk in the Spent Fuel Pool of a Nordic Boiling Water Reactor
Wang et al. SBLOCA initiated emergency condition analysis for a China three-loop PWR
Shin et al. Performance Analysis for a 12-finger CEA Drop Test of the SHN Unit 1
Alharbi et al. Evaluation of Total Loss of Reactor Coolant Flow for an Advanced Integral Reactor, SMART
Kang et al. Preliminary Analysis of Interfacing Systems LOCA from a Fire Event PSA Perspective
Harrington et al. Scram discharge volume break studies accident sequence analysis
Yi et al. Research on ultimate response guidelines (URGs) of floating nuclear power plant
Lohnert The corrosional and nuclear effects of water ingress into the primary circuit of an HTR-module
Gauntt Fukushima Unit 2 RCIC Operation and Proposed Full Scale Testing.
Cheng et al. Nuclear power accidents and its development prospects
Ullrich et al. Investigations of Anticipated Transients Without Reactor Scram and Other Selected Safety Devices
Williams et al. The power of simplification: Operator interface with the AP1000 {sup R} during design-basis and beyond design-basis events
Sohor et al. ANALYSIS OF A STUCK OPEN PORV IN THE PRESSURIZER OF THE MAINE YANKEE REACTOR