Ding et al., 2023 - Google Patents
General methodology for gas monitoring of cladding failure in sodium-cooled fast reactorsDing et al., 2023
View PDF- Document ID
- 7240195379969513965
- Author
- Ding C
- Filliatre P
- Desgranges L
- Publication year
- Publication venue
- Nuclear Engineering and Design
External Links
Snippet
A gas detection system (DRG) is designed in the sodium-cooled fast reactor (SFR) to limit the release of fissile material into the coolant. The system monitors a fission gas signal in the cover gas resulting from a cladding failure. We developed a general methodology to …
- 238000000034 method 0 title abstract description 54
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/02—Devices or arrangements for monitoring coolant or moderator
- G21C17/04—Detecting burst slugs
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/02—Devices or arrangements for monitoring coolant or moderator
- G21C17/022—Devices or arrangements for monitoring coolant or moderator for monitoring liquid coolants or moderators
- G21C17/0225—Chemical surface treatment, e.g. corrosion
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N23/00—Investigating or analysing materials by the use of wave or particle radiation not covered by G01N21/00 or G01N22/00, e.g. X-rays or neutrons
- G01N23/02—Investigating or analysing materials by the use of wave or particle radiation not covered by G01N21/00 or G01N22/00, e.g. X-rays or neutrons by transmitting the radiation through the material
- G01N23/04—Investigating or analysing materials by the use of wave or particle radiation not covered by G01N21/00 or G01N22/00, e.g. X-rays or neutrons by transmitting the radiation through the material and forming a picture
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N23/00—Investigating or analysing materials by the use of wave or particle radiation not covered by G01N21/00 or G01N22/00, e.g. X-rays or neutrons
- G01N23/02—Investigating or analysing materials by the use of wave or particle radiation not covered by G01N21/00 or G01N22/00, e.g. X-rays or neutrons by transmitting the radiation through the material
- G01N23/06—Investigating or analysing materials by the use of wave or particle radiation not covered by G01N21/00 or G01N22/00, e.g. X-rays or neutrons by transmitting the radiation through the material and measuring the absorption
-
- 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
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N33/00—Investigating or analysing materials by specific methods not covered by the preceding groups
- G01N33/20—Investigating or analysing materials by specific methods not covered by the preceding groups metals
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/06—Devices or arrangements for monitoring or testing fuel or fuel elements outside the reactor core, e.g. for burn-up, for contamination
-
- 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
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N2223/00—Investigating materials by wave or particle radiation
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21G—CONVERSION OF CHEMICAL ELEMENTS; RADIOACTIVE SOURCES
- G21G1/00—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes
Similar Documents
Publication | Publication Date | Title |
---|---|---|
Zoia et al. | Alpha eigenvalue calculations with Tripoli-4® | |
Coble et al. | Review of candidate techniques for material accountancy measurements in electrochemical separations facilities | |
Cechet et al. | A new burn-up module for application in fuel performance calculations targeting the helium production rate in (U, Pu) O2 for fast reactors | |
Verma et al. | Defective PWR fuel rods detection and characterization using an Artificial Neural Network | |
Mercatali et al. | Simulation of low-enriched uranium burnup in Russian VVER-1000 reactors with the Serpent Monte-Carlo code | |
Lewis et al. | Modelling the activity of 129I in the primary coolant of a CANDU reactor | |
Ding et al. | General methodology for gas monitoring of cladding failure in sodium-cooled fast reactors | |
Ebiwonjumi et al. | Validation of nuclide depletion capabilities in Monte Carlo code MCS | |
Giaccardi et al. | Towards modelling defective fuel rods in TRANSURANUS: Benchmark and assessment of gaseous and volatile radioactive fission product release | |
Trellue et al. | Spent fuel nondestructive assay integrated characterization from active neutron, passive neutron, and passive gamma | |
Zu et al. | Uncertainty analysis of infinite multiplication factor and nuclide number density based on the UAM-PWR benchmark with respect to cross sections, fission yields and decay half-life | |
Remeikis et al. | Indirect assessment of 135Cs activity in the ventilation system of the Ignalina NPP RBMK-1500 reactor | |
Beyer | Methodology estimating number of failed fuel rods and defect size | |
Seo et al. | Sensitivity analysis of cesium and strontium release from TRISO particle under irradiation and high temperature conditions | |
Szalóki et al. | Time-dependent leakage model for the identification of defective fuel assemblies of VVER-type nuclear reactors, part 1: Theory | |
Cassata et al. | Noble gas constraints on spent fuel irradiation histories | |
Bachchan et al. | Numerical simulation of localization of a sub-assembly with failed fuel pins in the prototype fast breeder reactor | |
Jermolajev et al. | Implementation of the indirect assessment method for 129I and 135Cs accumulation in the RBMK-1500 reactor coolant purification system | |
Ding et al. | How could fuel corrosion influence the delayed neutron signal time evolution in sodium cooled fast reactors? | |
Burkhardt et al. | Spatially-variant isotope production burnup modeling in a CANDU-6 reactor for nuclear treaty monitoring | |
Arkani | Diagnostic methods applied to Esfahan light water subcritical reactor (ELWSCR) | |
Bhandari et al. | Determination of spectrum shaping factor in nuclear reactor AHWR-CF by Monte Carlo method for material characterization using neutrons | |
Ernoult et al. | Automated selection of nuclides and reactions of interest in a depletion simulation. Precision loss estimation for multiple outputs | |
Svetachev et al. | Experimental studies of fission product release from model fuel elements at the physical start-up of the IVG. 1M research reactor | |
Ding | Multiphysical study of cladding failure detection in Sodium cooled Fast Reactors |