Gray, 1960 - Google Patents
Neutron flux measurement at elevated temperaturesGray, 1960
- Document ID
- 17976732815482806176
- Author
- Gray A
- Publication year
- Publication venue
- Nuclear Eng.
External Links
Snippet
The problems of neutron flux measurements in hightemperature, low-flux (zero-energy) reactors are discussed. Because of the low flux, the detectors must operate closer to the core than in power reactors and hence must withstand higher temperatures for long periods of …
- 230000004907 flux 0 title abstract description 23
Classifications
-
- 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
- G21C3/04—Constructional details
- G21C3/06—Casings; Jackets
-
- 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
-
- 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
- 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
- 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
- G21C1/00—Reactors
- G21C1/04—Thermal reactors; Epithermal reactors
- G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
-
- 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
-
- 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
- G21Y2004/00—SOLUTION
- G21Y2004/10—Compositions
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
-
- 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
-
- 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
- G21Y2002/201—Inadequate efficiency
-
- 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
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
Similar Documents
Publication | Publication Date | Title |
---|---|---|
Schluderberg et al. | Gaseous suspensions--a new reactor coolant | |
Gray | Neutron flux measurement at elevated temperatures | |
Thaler | Measurement of capsule heat transfer gaps using neutron radiography | |
Fortescue | Coolant choice for the vht reactor | |
Donaldson | ANALYSIS OF STRESSES IN THE CENTRAL PORTION OF MONEL-CLAD FUEL ELEMENTS DURING THERMAL CYCLING | |
Fraas et al. | Preliminary Design of a 10-Mw (t) Pebble-Bed Reactor Experiment | |
Newell | ESTIMATES OF THE RATE OF INTERNAL HEAT GENERATION IN SEVERAL RESEARCH REACTOR FACILITIES | |
Robertson et al. | Some" flux peaking" experiments in cluster type fuel rods | |
Coobs et al. | SPECIFICATIONS AND DRAWINGS FOR THE CONTROL RODS FOR THE EXPERIMENTAL GAS-COOLED REACTOR | |
Han | REPLACEMENT OF FUEL BY GRADUATED ZONE OF IRRADIATION | |
Stehle et al. | METHOD AND MEANS FOR ASSAYING FUEL ELEMENTS WHICH WERE MANUFACTURED BY SERIES | |
Smidt | HEAT REMOVAL FROM GAS-COOLED POWER REACTORS | |
Gronroos | CRITICALITY CALCULATIONS FOR A FAST LIQUID-METAL-COOLED REACTOR--PHASE I | |
Manly et al. | THE EXPERIMENTAL GAS-COOLED REACTOR | |
Cin et al. | GAS COOLED REACTOR VESSEL STUDY | |
Calori | Thermal Problems in Heterogeneous Systems; PROBLEMI TERMICI NELLE STRUTTURE ETEROGENEE | |
Katz | TEMPERATURE DISTRIBUTION IN EBOR FUEL RODS DUE TO NON-UNIFORM CIRCUMFERENTIAL COOLING | |
De Raedt et al. | Two-dimensional neutron and gamma calculations for devices irradiated in BR2 reflector positions | |
Banks | EGCR-Descendant of Calder Hall | |
Goff Jr | Design Test 1112: interim test results, NPR production horizontal rod and drive assembly | |
Banks | Sensitivity of Nuclear Fuel Costs to Selection of Coolant Gas | |
Bella | PRESENT TRENDS IN NUCLEAR FUELS | |
Tolson et al. | THE MANUFACTURE OF EGCR CORE 1 FUEL ASSEMBLIES | |
Horsley et al. | TEMPERATURE PREDICTION AND CONTROL IN PRODUCTION REACTORS | |
Schmidl et al. | A Transfer Function Model of the HBWR Plant |