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

Smolentsev, 2021 - Google Patents

Design window for open-surface lithium divertor with helium-cooled substrate

Smolentsev, 2021

View HTML
Document ID
9835806428208052943
Author
Smolentsev S
Publication year
Publication venue
Fusion Engineering and Design

External Links

Snippet

This study for an open-surface flowing lithium (Li) divertor with a thin helium-cooled substrate includes a scaling analysis, numerical computations and an analytical solution to access the design window for a low vaporization divertor option where the maximum …
Continue reading at www.sciencedirect.com (HTML) (other versions)

Classifications

    • 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 GASES [GHG] EMISSION, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors
    • Y02E30/40Other aspects relating to nuclear fission
    • 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 GASES [GHG] EMISSION, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/10Fusion reactors
    • Y02E30/12Magnetic plasma confinement [MPC]
    • 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 GASES [GHG] EMISSION, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/10Fusion reactors
    • Y02E30/18Low temperature fusion, e.g. "cold fusion"
    • 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 GASES [GHG] EMISSION, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors
    • Y02E30/34Fast breeder reactors

Similar Documents

Publication Publication Date Title
Abdou et al. On the exploration of innovative concepts for fusion chamber technology
LaBombard et al. ADX: a high field, high power density, advanced divertor and RF tokamak
Nygren et al. A fusion reactor design with a liquid first wall and divertor
Esmaili et al. Analysis of likelihood of lower head failure and ex-vessel fuel coolant interaction energetics for AP1000
Norajitra et al. Divertor conceptual designs for a fusion power plant
Smolentsev Design window for open-surface lithium divertor with helium-cooled substrate
Park et al. Pre-conceptual design study on K-DEMO ceramic breeder blanket
Abdou et al. Overview of fusion blanket R&D in the US over the last decade
Smolentsev et al. Integrated liquid metal flowing first wall and open-surface divertor for fusion nuclear science facility: concept, design, and analysis
Huang et al. Tungsten monoblock concepts for the Fusion Nuclear Science Facility (FNSF) first wall and divertor
Xie et al. Evaluation of tritium burnup fraction for CFETR scenarios with core-edge coupling simulations
Liu et al. Study on the temperature control mechanism of the tritium breeding blanket for CFETR
Asakura et al. Recent progress of plasma exhaust concepts and divertor designs for tokamak DEMO reactors
Kolemen et al. Design of the flowing liquid torus (FLIT)
Kirillov et al. Liquid lithium self-cooled breeding blanket design for ITER
Lu et al. Progress on neutronic analysis for CFETR
Gałązka et al. Numerical analyses of JT-60SA tokamak with tungsten divertor by COREDIV code
Nygren et al. Design integration of liquid surface divertors
Smolentsev et al. Status and progress of liquid metal thermofluids modeling for the US fusion nuclear science facility
Wu et al. Heat transfer effectiveness for cooling of Canadian SCWR fuel assembly under the LOCA/LOECC scenario
Mantha et al. Intense heat simulation studies on window of high density liquid metal spallation target module for accelerator driven systems
Zhu et al. Refined multiphysics analysis of W7-X cryopumps
Lian et al. Neutronics influence of poloidal nonuniform neutron wall loading on helium-cooled ceramic breeder blanket for CFETR
Lee et al. Reduction of circulation power for helium-cooled fusion reactor blanket using additive CO2 gas
Kunugi et al. Direct numerical simulation of turbulent free-surface high Prandtl number fluid flows in fusion reactors