Pool et al., 1990 - Google Patents
Single Shell Tank Waste Characterization Project for Tank B-110, Core 9-data package and PNL validation summary reportPool et al., 1990
- Document ID
- 5027941196835974909
- Author
- Pool K
- Jones T
- McKinley S
- Tingey J
- Longaker T
- Gibson J
- Publication year
External Links
Snippet
This Data Package contains results obtained by Pacific Northwest Laboratory (PNL) staff in the characterization and analyses of Core 9 segments taken from the Single-Shell Tank (SST) 110B. The characterization and analysis of Core 9 segments are outlined in the Waste …
- 238000010192 crystallographic characterization 0 title abstract description 18
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
-
- 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
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N1/00—Sampling; Preparing specimens for investigation
- G01N1/28—Preparing specimens for investigation including physical details of (bio-)chemical methods covered elsewhere, e.g. G01N33/50, C12Q
-
- 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
-
- 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
- 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
- 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
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| Pool et al. | Single Shell Tank Waste Characterization Project for Tank B-110, Core 9-data package and PNL validation summary report | |
| Freely et al. | Annual report of the surface air sampling program | |
| Cowder et al. | Compact K-edge densitometer | |
| MARTINO | Tank 10H Saltcake Core Sample Analysis | |
| Barnes et al. | Monitoring the Possible Effects of Corroding Fuel Cladding in Nuclear Ponds: a Modified ROV for Storage Ponds-20144 | |
| McNair et al. | Characterization Techniques for TRU Waste from the Analytical Laboratory Hot Cells at Idaho National Laboratory-19610 | |
| Hudgens | Selection and testing of materials for use in a flow-through liquid sampling cell for x-ray fluorescence analysis of special nuclear materials in dissolver solution | |
| Jedlovec | X-ray-fluorescence and bob-displacer-system design specification for application in the Wet Scrap Design Laboratory. Final report for GFY 1980.[ATERIAL BALANCE] | |
| Gerber et al. | SAF line analytical chemistry system | |
| Stephens et al. | Methods for the accountability of mixed oxide | |
| Strohm et al. | Nondestructive evaluation of sampling error for plutonium assay | |
| Henderson et al. | Energy-dispersive x-ray-fluorescence analysis for on-line uranium-concentration measurement | |
| Stanley et al. | Characterization of weapons-legacy Pu-contaminated waste for disposal at WIPP | |
| Strohm et al. | Demonstration of the in-field use of calorimetric assay for IAEA inspection purposes | |
| Gutmacher | Measurement uncertainty estimates for reprocessing facilities | |
| Filby et al. | Nuclear material accountability by isotope dilution mass spectrometry | |
| Johns et al. | Manually controlled neutron-activation system | |
| Cuypers et al. | PERLA: A laboratory for training and performance assessment of safeguards techniques | |
| Elmont et al. | Quantitative estimate of holdup in a plutonium processing facility | |
| Pillay et al. | International safeguards for an automated MOX (mixed-oxide) fuel fabrication facility | |
| Branam | Temperature measurement and sampling probes for the UF/sub 6/homogenization study | |
| Hochel | A totally automatic density meter for radioactive solutions | |
| Van Siclen | Radioactive waste examination pilot plant | |
| Cronenberg et al. | Tellurium release, transport, and deposition behavior noted from integral fuels testing | |
| Cardwell et al. | Gas-phase sampling of UF6 cylinders in international safeguards |