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

Li et al. - Google Patents

Strategy Study on Treatment and Disposal of the Radioactive Graphite Waste of HTR

Li et al.

View PDF
Document ID
1737608588429959004
Author
Li J
Ma T
Wang J

External Links

Snippet

The possible options to change HTGR spent fuel into an acceptable form for repository disposal were discussed. The progresses of physical, chemical, and electrochemical separation of graphite from the HTGR fuel elements were reviewed. The advantages and …
Continue reading at inis.iaea.org (PDF) (other versions)

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/28Treating solids
    • G21F9/30Processing
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/28Treating solids
    • G21F9/34Disposal of solid waste
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C19/00Arrangements 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
    • G21C19/42Reprocessing of irradiated fuel
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F5/00Transportable or portable shielded containers
    • G21F5/005Containers for solid radioactive wastes, e.g. for ultimate disposal
    • G21F5/008Containers for fuel elements
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/42Selection of substances for use as reactor fuel
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02Fuel elements
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/04Treating liquids
    • G21F9/06Processing
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/04Treating liquids
    • G21F9/20Disposal of liquid waste
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C19/00Arrangements 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
    • G21C19/34Apparatus or processes for dismantling nuclear fuel, e.g. before reprocessing; Apparatus or processes for dismantling strings of spent fuel elements

Similar Documents

Publication Publication Date Title
JP6220329B2 (en) Particulate metal fuel used in power generation, recycling system, and small modular reactor
EP2769384B1 (en) Graphite thermal decontamination with reducing gases
Chidambaram et al. Plutonium and thorium in the Indian nuclear programme
Bushuev et al. Radioactive contamination of spent reactor graphite
Li et al. Strategy Study on Treatment and Disposal of the Radioactive Graphite Waste of HTR
US9040014B2 (en) Graphite thermal decontamination with reducing gases
El-Hinnawi Review of the environmental impact of nuclear energy
Yim et al. Generation of Nuclear Waste from Nuclear Power
Li Treatment and Disposal of the Radioactive Graphite Waste of High-Temperature Gas-Cooled Reactor Spent Fuel
Tian et al. Treatment and disposal of the radioactive graphite waste
Hoogen et al. Evaluation of potential head-end procedures for graphite-containing fuel elements
Kitcher A White Paper: Disposition Options for a High-Temperature Gas-Cooled Reactor
Kiegiel et al. Management of Radioactive Waste from HTGR Reactors Including Spent TRISO Fuel—State of the Art. Energies 2022, 15, 1099
JP3242297U (en) A safety metal container device with a CVD diamond semiconductor nuclear battery.
Kulcinski et al. Safety and Environmental Characteristics of Recent D-3He and DT Tokamak Power Reactors
Şahin et al. Utilization of reactor grade plutonium as energy multiplier in the LIFE engine
KR101522980B1 (en) Yttrium Tri-iodide Target for Nuclear Transmutation of Nuclide Iodine-129 and the Manufacturing Method thereof, and Treatment System for Nuclide Iodine-129 using It
Nabielek¹ et al. Ceramic coated particles for safe operation in HTRS and in long-term storage
McEnaney et al. Planning for disposal of irradiated graphite: Issues for the new generation of HTRs
Palliser Nuclear energy.
Barré Nuclear Power
Chapelot et al. Requirements for high temperature reactor fuel particle design assessment
Sawa et al. Study on storage and reprocessing concept of the high temperature engineering test reactor (HTTR) fuel
Baker et al. Safety considerations in the fast reactor fuel cycle
Márquez et al. GRAFEC: A New Spanish Program to Investigate Waste Management Options for Radioactive Graphite-12399