[go: up one dir, main page]

Gentzlinger et al., 1991 - Google Patents

A guideline for design, analysis, and fabrication of vacuum vessels for cryogenic accelerators

Gentzlinger et al., 1991

View PDF
Document ID
3804574464797110649
Author
Gentzlinger R
Christensen K
Publication year
Publication venue
Conference Record of the 1991 IEEE Particle Accelerator Conference

External Links

Snippet

This paper describes a methodology for designing, analyzing, and fabricating vacuum vessels that fulfill the unique requirements of cryogenic accelerators. Included is a design approach that allows the vessel to meet the intent of the American Society of Mechanical …
Continue reading at epaper.kek.jp (PDF) (other versions)

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C13/00—Pressure vessels; Containment vessels; Containment in general
    • G21C13/02—Details
    • G21C13/032—Joints between tubes and vessel walls, e.g. taking into account thermal stresses
    • G21C13/036—Joints between tubes and vessel walls, e.g. taking into account thermal stresses the tube passing through the vessel wall, i.e. continuing on both sides of the wall
    • 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

Similar Documents

Publication Publication Date Title
Cheverton et al. Evaluation of HFIR (High Flux Isotope Reactor) pressure-vessel integrity considering radiation embrittlement
EP3384198B1 (en) Pipe restraint and shield
Gentzlinger et al. A guideline for design, analysis, and fabrication of vacuum vessels for cryogenic accelerators
Winterfeldt et al. Redesign of the vulcain 2 nozzle extension
Błachut et al. Burst pressures for toriconical shells: experimental and numerical approach
De Meis RCC-MRx design code for nuclear components
Bouzid et al. On the strength and tightness of ASME B16. 5 and B16. 47 series a standard flanges
Bartholomé ‘German leak-before-break concept’(description of German LBB procedures, practices and applications)
Choi et al. Fatigue life assessment of reactor coolant system components by using transfer functions of integrated FE model
Bouzid et al. Integrity and leak tightness of ASME B. 16.5 and B. 16.47 flanges used in nuclear piping systems
Rosenblad et al. Hydrogen Transfer Line Structural Analysis
Cancemi et al. Pipe Performance in Long Term Operation Framework: Ageing Issues
Kalra et al. Study the Integrity of Flange to Gasket Connection Using ASME PCC-1 Under Bolt Tightening and Operating Condition
Batul et al. Application of structural similitude for scaling of a pressure vessel
Bartholomé et al. Application of Leak-Before-Break Concept in VVER 440-230: Results and consequences for TACIS-program 91/1.2
Smith et al. Steam Turbine Casing Analyses to Determine Pressure and Temperature Limits
Gay et al. Jules Horowitz Reactor: RCC-MRx (1) applicability for the design phase of experimental devices
Narug et al. Application of the ASME Boiler and Pressure Vessel Code in the Design of SRF Cavities at Fermilab
Kearney et al. Mechanical and thermal design of a gas-cooled fusion blanket module
Eryilmaz Modeling of Casing Containment in an Overspeeding Turbine Stage
Smith III US Contributions to the ITER Vacuum Auxiliary System
Ebrahimi et al. A Novel Approach for Assessment of Pressurised Equipment for Slow Depressurisation During Fire
Nakamura et al. Evaluation method for structural integrity assessment in core disruptive accident of fast reactor
Gonzalez-Teodoro et al. Progress on the Design Development for Hard Core Components for USDA Diagnostics at ITER
Bangash et al. Steel Pressure Vessels for Nuclear Facilities