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

MILDON, 2003 - Google Patents

Thermal analysis of large diameter container (LDC) with alternate loadings of KE Basin sludge

MILDON, 2003

Document ID
7955092102887545378
Author
MILDON D
Publication year

External Links

Snippet

A thermal analysis was performed to determine temperature distribution and hydrogen generation for a Large Diameter Container (LDC) having a two layer load configuration made up of a lower layer, consisting of sludge from the weasel pit, and an upper layer …
Continue reading at www.osti.gov (other versions)

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/28—Treating solids
    • G21F9/30—Processing
    • G21F9/301—Processing by fixation in stable solid media
    • G21F9/307—Processing by fixation in stable solid media in polymeric matrix, e.g. resins, tars
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/28—Treating solids
    • G21F9/34—Disposal of solid waste
    • G21F9/36—Disposal of solid waste by packaging; by baling
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F5/00—Transportable or portable shielded containers
    • G21F5/005—Containers for solid radioactive wastes, e.g. for ultimate disposal
    • G21F5/008—Containers for fuel elements
    • 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
    • G21C3/02—Fuel elements
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/04—Treating liquids
    • G21F9/20—Disposal of liquid waste
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/42—Reprocessing of irradiated fuel
    • 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
    • G21C3/42—Selection of substances for use as reactor fuel
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F1/00—Shielding characterised by the composition of the materials
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21Y—INDEXING SCHEME RELATING TO NUCLEAR REACTORS, POWER PLANTS AND EXPLOSIVES, TO PROTECTION AGAINST RADIATION, TO THE TREATMENT OF RADIOACTIVELY CONTAMINATED MATERIAL, TO APPLICATIONS OF RADIOACTIVE SOURCES AND TO THE UTILISATION OF COSMIC RADIATION
    • G21Y2002/00—PROBLEM
    • G21Y2002/104—Inadequate performance, deformation, cracks, rupture

Similar Documents

Publication Publication Date Title
Kurata et al. Step-by-step challenge of debris characterization for the decommissioning of Fukushima-Daiichi Nuclear Power Station (FDNPS)
Kiegiel et al. Management of Radioactive Waste from HTGR Reactors including Spent TRISO Fuel—State of the Art
Stone Fukushima cleanup will be drawn out and costly
Knebel et al. A review of revaporisation behaviour of radioactive Cs deposits and its impact on the source term in severe nuclear accidents from Phébus FP results and single effect testing
Van Snyder Finely Divided Metal as Nuclear Reactor Fuel
MILDON Thermal analysis of large diameter container (LDC) with alternate loadings of KE Basin sludge
Loukusa et al. Feasibility of KBS-3 spent fuel disposal concept for Norwegian spent fuel
Makenas et al. Analysis of sludge from Hanford K East Basin canisters
Johnson Thermal Analysis of Sludge Transportation System for Transportation of KE NLOP Sludge
RITTMANN Evaluation of KE Basin Sludge Radioisotopics & Volumes in Support of the Sludge Water System Safety Analysis [SEC 1 & 2]
HEARD et al. Safety-Basis Thermal Analysis for KE Basin Sludge Transport and Storage
Garrett et al. Treatment of Problematic Reactive Metal Wastes Using the GeoMelt {sup R} In-Container Vitrification (ICV {sup TM}) Process-20326
PIEPHO Design Calculations for Gas Flow & Diffusion Behavior in the Large Diameter Container & Cask
SHELOR Gas behavior in Large Diameter Containers (LDC) during and following loading with 105K East sludge
DUNCAN Physical Behavior of Uranium Metal Bearing Hanford K East Basin Sludge Materials
Quintero et al. Retrieval and Management of TRU Sludge at Hanford K-Basin-19641
Gregg et al. ANSTO Synroc Wasteforms for the Immobilization of a Range of Mo-99 Production Wastes-19326
Owen et al. Fission Product Transport at Three Mile Island
Himes Estimates of Radiation Dose Rates Near Large Diameter Sludge Containers in T Plant
HEARD Thermal Analysis for T Plant Process Cell Freeze Potential & Over Filled Large Diameter Containers
Forsberg et al. Cermet Spent Nuclear Fuel Casks and Waste Packages
Wicks et al. Chemical durability of Savannah River Plant waste glass as a function of groundwater pH
PACKER Evaluation of Helium Purge & Vent Process to Reduce Hydrogen Concentrations in the Large Diameter Container & Cask Void Volumes at T Plant
King et al. Evaluation of zeolite mixtures for decontamination of high-activity-level water in the Submerged Demineralizer System (SDS) flowsheet at the Three Mile Island Nuclear Power Station, Unit 2
Williams et al. Radiolysis studies in support of the remediation of the Molten Salt Reactor Experiment