[go: up one dir, main page]

Butt et al., 2016 - Google Patents

Using reactor grade plutonium in PWR: CORAIL and IMF options

Butt et al., 2016

Document ID
9697562992160698685
Author
Butt H
Saleem C
Ahmad M
Publication year
Publication venue
2016 International Conference on Emerging Technologies (ICET)

External Links

Snippet

In nuclear reactors, plutonium is continuously being produced due to the presence of U-238 in the fuel. The need of the hour is to look for the ways to utilize this plutonium to overcome the uranium fuel shortages in future. To utilize the plutonium inventory from these reactors …
Continue reading at ieeexplore.ieee.org (other versions)

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/30Assemblies of a number of fuel elements in the form of a rigid unit
    • G21C3/32Bundles of parallel pin-, rod-, or tube-shaped fuel elements
    • G21C3/326Bundles of parallel pin-, rod-, or tube-shaped fuel elements comprising fuel elements of different composition; comprising, in addition to the fuel elements, other pin-, rod-, or tube-shaped elements, e.g. control rods, grid support rods, fertile rods, poison rods or dummy rods
    • 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
    • Y02E30/38Fuel
    • 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
    • G21C3/04Constructional details
    • 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
    • Y02E30/30Nuclear fission reactors
    • Y02E30/34Fast breeder reactors
    • 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
    • Y02E30/39Control of nuclear reactions
    • 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
    • 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
    • Y02E30/31Boiling water reactors
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C1/00Reactors
    • G21C1/02Fast fission reactors, i.e. reactors not using a moderator; Metal cooled reactors; Fast breeders
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21YINDEXING 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
    • G21Y2004/00SOLUTION
    • G21Y2004/10Compositions
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21YINDEXING 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
    • G21Y2002/00PROBLEM
    • G21Y2002/201Inadequate efficiency
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21YINDEXING 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
    • G21Y2002/00PROBLEM
    • G21Y2002/104Inadequate performance, deformation, cracks, rupture
    • 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
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21YINDEXING 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
    • G21Y2004/00SOLUTION
    • G21Y2004/30Improving a design
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C7/00Control of nuclear reaction
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C5/00Moderator or core structure; Selection of materials for use as moderator
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21DNUCLEAR POWER PLANT
    • G21D3/00Control of nuclear power plant
    • G21D3/001Computer implemented control

Similar Documents

Publication Publication Date Title
Khoshahval et al. Evaluation of burnable absorber rods effect on neutronic performance in fuel assembly of WWER-1000 reactor
Trellue et al. Neutronics and material attractiveness for PWR thorium systems using monte carlo techniques
Ibrahim et al. Analysis of thorium fuel feasibility in large scale gas cooled fast reactor using MCNPX code
Hossain et al. Neutronic and fuel cycle performance of VVER-1000 for dual cooled annular fuel with coated burnable poison
Kabach et al. The use of burnable absorbers integrated into TRISO/QUADRISO particles as a reactivity control method in a pebble-bed HTR reactor fuelled with (Th, 233U) O2
Benrhnia et al. Neutronic and burnup characteristics of potential dual‐cooled annular (Th‐233U‐235U) O2 fuel for the advanced pressurized water reactors: An assembly‐level analysis
Akbari et al. Analysis of thorium-transuranic fuel deployment in a LW-SMR: A solution toward sustainable fuel supply for the future plants
Shwageraus et al. Microheterogeneous thoria-urania fuels for pressurized water reactors
Wang Optimization of a seed and blanket thorium-uranium fuel cycle for pressurized water reactors
Hong et al. Physics study of deep-burning of spent fuel transuranics using commercial LWR cores
Haas et al. Fuel cycle strategies and plutonium management in Europe
Kim et al. Fuel cycle analysis of once-through nuclear systems.
Reda et al. Neutronic Performance of the VVER‐1000 Reactor Using Thorium Fuel with ENDF Library
Merk et al. On the use of a moderation layer to improve the safety behavior in sodium cooled fast reactors
Cho et al. Physics analysis of new TRU recycling options using FCM and MOX fueled PWR assemblies
Mohamed et al. Use of Thorium-Plutonium MOX in the inner pins of CANDU fuel bundles
Niloy et al. Neutronic analysis of ABR-1000 sodium cooled fast reactor with radially and axially heterogeneous core configurations
Galahom Improving the neutronic characteristics of a boiling water reactor by using uranium zirconium hydride fuel instead of uranium dioxide fuel
Martinez et al. Comparison of BWR fuel assembly options for minor actinide recycling
Lindley The use of reduced-moderation light water reactors for transuranic isotope burning in thorium fuel
Liem et al. Burnup performance of small-sized long-life CANDLE high temperature gas-cooled reactors with U–Th–Pa fuel
Galahom et al. Study the neutronic analysis and burnup for BWR fueled with hydride fuel using MCNPX code
Syarifah et al. The prospect of uranium nitride (UN) and mixed nitride fuel (UN-PuN) for pressurized water reactor
Nabila et al. An attempt to find the optimal loading pattern of minor actinides in the PWR fuel rods
Galahom et al. Design of an MCNPX model to simulate the performance of BWRs using thorium as fuel and its validation with HELIOS code