Calculated critical parameters in simple geometries for oxide and nitrate water mixtures of U-233, U-235 and Pu-239 with thorium. Final report
Calculations have been performed on water mixtures of oxides and nitrates of /sup 233/U, /sup 235/U, and /sup 239/Pu with chemically similar thorium compounds to determine critical dimensions for simple geometries (sphere, cylinder, and slab). Uranium enrichments calculated were 100%, 20%, 10%, and 5%; plutonium calculations assumed 100% /sup 239/Pu. Thorium to uranium or plutonium weight ratios (Th: U or Pu) calculated were 0, 1, 4, and 8. Both bare and full water reflection conditions were calculated. The results of the calculations are plotted showing a critical dimension versus the uranium or plutonium concentration. Plots of K-infinity and material buckling for each material type are also shown.
- Research Organization:
- Battelle Pacific Northwest Labs., Richland, WA (United States)
- DOE Contract Number:
- EY-76-C-06-1830
- OSTI ID:
- 5748642
- Report Number(s):
- PNL-2080-16; TRN: 80-004384
- Country of Publication:
- United States
- Language:
- English
Similar Records
THE INDEPENDENT YIELD OF $sup 96$Nb IN THE THERMAL NEUTRON FISSION OF $sup 233$U, $sup 235$U, AND $sup 239$Pu
Calculations of k for Some Small U233-, U235-, and Pu239-Fueled Fast Reactors
Evaluation of the thermal-neutron constants for /sup 233/U, /sup 235/U, /sup 239/Pu and /sup 241/Pu
Journal Article
·
Wed Feb 01 00:00:00 EST 1961
· J. Inorg. & Nuclear Chem.
·
OSTI ID:5748642
Calculations of k for Some Small U233-, U235-, and Pu239-Fueled Fast Reactors
Technical Report
·
Sat Feb 01 00:00:00 EST 1964
·
OSTI ID:5748642
Evaluation of the thermal-neutron constants for /sup 233/U, /sup 235/U, /sup 239/Pu and /sup 241/Pu
Technical Report
·
Fri Jan 01 00:00:00 EST 1982
·
OSTI ID:5748642
Related Subjects
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
42 ENGINEERING
PLUTONIUM NITRATES
CRITICALITY
PLUTONIUM OXIDES
URANIUM NITRATES
URANIUM OXIDES
AQUEOUS SOLUTIONS
CRITICAL SIZE
CYLINDRICAL CONFIGURATION
PLUTONIUM 239
REPROCESSING
SLABS
SPHERICAL CONFIGURATION
THORIUM NITRATES
URANIUM 233
URANIUM 235
ACTINIDE COMPOUNDS
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
CHALCOGENIDES
CONFIGURATION
DISPERSIONS
EVEN-ODD NUCLEI
HEAVY NUCLEI
ISOMERIC TRANSITION ISOTOPES
ISOTOPES
MINUTES LIVING RADIOISOTOPES
MIXTURES
NITRATES
NITROGEN COMPOUNDS
NUCLEI
OXIDES
OXYGEN COMPOUNDS
PLUTONIUM COMPOUNDS
PLUTONIUM ISOTOPES
RADIOISOTOPES
SEPARATION PROCESSES
SIZE
SOLUTIONS
THORIUM COMPOUNDS
TRANSURANIUM COMPOUNDS
URANIUM COMPOUNDS
URANIUM ISOTOPES
YEARS LIVING RADIOISOTOPES
050800* - Nuclear Fuels- Spent Fuels Reprocessing
054000 - Nuclear Fuels- Health & Safety
420203 - Engineering- Handling Equipment & Procedures
42 ENGINEERING
PLUTONIUM NITRATES
CRITICALITY
PLUTONIUM OXIDES
URANIUM NITRATES
URANIUM OXIDES
AQUEOUS SOLUTIONS
CRITICAL SIZE
CYLINDRICAL CONFIGURATION
PLUTONIUM 239
REPROCESSING
SLABS
SPHERICAL CONFIGURATION
THORIUM NITRATES
URANIUM 233
URANIUM 235
ACTINIDE COMPOUNDS
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
CHALCOGENIDES
CONFIGURATION
DISPERSIONS
EVEN-ODD NUCLEI
HEAVY NUCLEI
ISOMERIC TRANSITION ISOTOPES
ISOTOPES
MINUTES LIVING RADIOISOTOPES
MIXTURES
NITRATES
NITROGEN COMPOUNDS
NUCLEI
OXIDES
OXYGEN COMPOUNDS
PLUTONIUM COMPOUNDS
PLUTONIUM ISOTOPES
RADIOISOTOPES
SEPARATION PROCESSES
SIZE
SOLUTIONS
THORIUM COMPOUNDS
TRANSURANIUM COMPOUNDS
URANIUM COMPOUNDS
URANIUM ISOTOPES
YEARS LIVING RADIOISOTOPES
050800* - Nuclear Fuels- Spent Fuels Reprocessing
054000 - Nuclear Fuels- Health & Safety
420203 - Engineering- Handling Equipment & Procedures