[go: up one dir, main page]
More Web Proxy on the site http://driver.im/

Damerell et al., 1993 - Google Patents

2D/3D program work summary report

Damerell et al., 1993

View PDF
Document ID
7819843545532109458
Author
Damerell P
Simons J
et al.
Publication year

External Links

Snippet

ABSTRACT The 2D/3D Program was carried out by Germany, Japan and the United States to investigate the thermal-hydraulics of a PWR large-break LOCA. A contributory approach was utilized in which each country contributed significant effort to the program and all three …
Continue reading at citeseerx.ist.psu.edu (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
    • Y02E30/34—Fast breeder reactors
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/02—Devices or arrangements for monitoring coolant or moderator
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
    • G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/24—Promoting flow of the coolant
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactors
    • G21C1/02—Fast fission reactors, i.e. reactors not using a moderator; Metal cooled reactors; Fast breeders

Similar Documents

Publication Publication Date Title
Tenchine Some thermal hydraulic challenges in sodium cooled fast reactors
Damerell et al. 2D/3D program work summary report
Wang et al. Thermal hydraulic phenomena related to small break LOCAs in AP1000
Murao et al. Experimental study of system behavior during reflood phase of PWR-LOCA using CCTF
D'Auria et al. Use of a natural circulation map for assessing PWR performance
Ishii Investigation of Natural Circulation Instability and Transients in Passively Safe Small Modular Reactors
Takeda et al. Measurement of non-condensable gas in a PWR small-break LOCA simulation test with LSTF for OECD/NEA ROSA Project and RELAP5 post-test analysis
Takeda ROSA/LSTF test and RELAP5 code analyses on PWR steam generator tube rupture accident with recovery actions
Ha et al. Evaluations of two-phase natural circulation flow induced in the reactor vessel annular gap under ERVC conditions
Tuunanen et al. Analyses of PACTEL passive safety injection experiments GDE-21 through GDE-25
Damerell et al. 2D/3D Program work summary report,[January 1988--December 1992]
Böttcher et al. Detail CFD simulation of the integrated reactor pressure vessel of SMART
Grolmes et al. R-series loss-of-flow safety experiment in TREAT
Yu et al. Development of two-dimensional hydrogen distribution model in small-scale spaces under severe accidents
Pesetti et al. Test Section Design for SGTR Experimental Investigation in CIRCE Facility for HLMRS Supported by SIMMER-III Code
Kim et al. RELAP5/MOD3. 3 analysis of coolant depletion tests after safety injection failure during a large-break loss-of-coolant accident
Murase et al. BWR loss of coolant integral tests with two bundle loop,(I) thermal-hydraulic characteristics in parallel channels
Liang et al. Numerical simulation on transient thermal and hydraulic characteristics in sodium pool of CEFR under OPT-SLOOP and OPT-RHROSL conditions
Abdulrahman Natural circulation in a PWR for a sinusoidal heat input: analytical model
Adachi et al. Design of slab core test facility (SCTF) in large scale reflood test program, 1
Kovtonyuk et al. Safety of evolutionary reactors: feasibility study for the experimental program of SPES facility
Wolfert Scaling of Thermal-Hydraulic Phenomena and System Code Assessment
Puustinen Natural circulation flow behavior at reduced inventory in a VVER geometry
Tatu et al. Analysis of double-ended guillotine break at a direct vessel Injection line of ATLAS
D'Auria et al. Evaluation of the data base from the small break LOCA counterpart tests performed in LOBI, SPES, BETHSY and LSTF facilities