Nothing Special   »   [go: up one dir, main page]

Rimkevicius et al., 2002 - Google Patents

Safety assessment and improvement of Ignalina NPP against downcomer ruptures outside Accident Localisation System

Rimkevicius et al., 2002

View PDF
Document ID
5454564981692486010
Author
Rimkevicius S
Urbonavicius E
Publication year

External Links

Snippet

Accident Localisation System (ALS) of Ignalina NPP is a pressure suppression type confinement, designed to prevent the release of contaminated steam-water mixture to the environment in case of Loss-of-Coolant Accident (LOCA). One of the peculiarities of Ignalina …
Continue reading at www.osti.gov (PDF) (other versions)

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 GASES [GHG] EMISSION, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors
    • Y02E30/40—Other aspects relating to nuclear fission
    • 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 GASES [GHG] EMISSION, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors
    • Y02E30/32—Pressurized water reactors

Similar Documents

Publication Publication Date Title
JP2009098035A (en) Nuclear power plant
JPH09166687A (en) Boiling water reactor
Rimkevicius et al. Safety assessment and improvement of Ignalina NPP against downcomer ruptures outside Accident Localisation System
Mizokami et al. Event sequence of the Fukushima Daiichi accident
Cesna et al. Reactor cavity and ALS thermal-hydraulic evaluation in the case of fuel channels ruptures at Ignalina NPP
Uspuras et al. Development of accident management measures for RBMK-1500 in the case of loss of long-term core cooling
Muhlheim et al. Design Strategies and Evaluation for Sharing Systems at Multi-Unit Plants Phase I
Rimkevicius et al. Safety margins of RBMK-1500 accident localisation system at Ignalina NPP
Lee et al. Analyses of Fission Product Retention under ISLOCA using MELCOR for APR1400
Babilas et al. Simulation of containment hydrogen control system at Ignalina NPP
RU2107342C1 (en) Shielding system of water-moderated reactor unit containment
RU2106026C1 (en) Shielding system for water-moderated reactor containment
Khan et al. Analysis of the loss of coolant accident for LEU cores of Pakistan research reactor-1
Matejovic et al. Backfitting of Dukovany NPP for design extension conditions
Babilas et al. Analysis of the hydrogen behaviour in compartments of the Ignalina nuclear power plant
Kostka et al. Hydrogen mixing analyses for a VVER containment
Chang et al. Reassessment to prevent Flooding Hazard in the CPB
Collins Technical evaluation of the susceptibility of safety-related systems to flooding caused by the failure of non-Category I systems for Turkey Point Nuclear Power Plant, Units 3 and 4
Lv et al. Margin Analysis of Conventional Island Under Beyond Design Basis External Flooding Scenario for NPP
Miramon et al. Challenges To Develop and Draw Relevant Lessons From A Level 1 Internal Flooding PSA
RU2122246C1 (en) Containment shielding system for water-moderated reactor unit
Plant 2.4 SCOPING AND SCREENING RESULTS: STRUCTURES
Tkac Build-up the new confinement accident localisation system (SLH)
Ušpuras et al. Probabilistic and deterministic analysis of BDBA in RBMK-1500.
Huang et al. Modification to Shield Tank Overpressure Protection in a CANDU Reactor for Beyond Design Basis Event