Study of the /sup 233/U--/sup 232/Th reactor as a burner for actinide wastes
Conference
·
· Natl. Bur. Stand. (U.S.), Spec. Publ.; (United States)
OSTI ID:7290992
A plausible method for reducing the storage problems and hazards now associated with long-lived actinide wastes might be to recycle and convert these to fission products. Several reactor types can be envisaged for this purpose. It is noted that in a /sup 233/U-/sup 232/Th reactor, the production of /sup 237/Np, Pu and transplutonium isotopes is greatly reduced compared to a /sup 235/U-/sup 238/U reactor because several additional neutron captures are required to reach the same mass. Hence, the /sup 233/U-/sup 232/Th reactor can be employed to effectively reduce Np, Pu, Am and Cm wastes to fission-product wastes which entail shorter (approximately 1000 yr) storage times.
- Research Organization:
- Oak Ridge National Lab., TN
- OSTI ID:
- 7290992
- Conference Information:
- Journal Name: Natl. Bur. Stand. (U.S.), Spec. Publ.; (United States) Journal Volume: 1
- Country of Publication:
- United States
- Language:
- English
Similar Records
Fission of /sup 232/Th, /sup 233/U, /sup 235/U, /sup 236/U, /sup 238/U, /sup 237/Np, and /sup 239/Pu by electrons with energies between 100 and 275 MeV
Nuclear data sensitivity coefficients for A (/sup 233/U--/sup 232/Th) fueled LMFBR
The fission cross sections of /sup 230/Th, /sup 232/Th, /sup 233/U, /sup 234/U, /sup 236/U, /sup 238/U, /sup 237/Np, /sup 239/Pu and /sup 242/Pu relative /sup 235/U at 14. 74 MeV neutron energy
Journal Article
·
Mon Nov 30 23:00:00 EST 1981
· Sov. J. Nucl. Phys. (Engl. Transl.); (United States)
·
OSTI ID:5327445
Nuclear data sensitivity coefficients for A (/sup 233/U--/sup 232/Th) fueled LMFBR
Conference
·
Sat Dec 31 23:00:00 EST 1977
·
OSTI ID:6747648
The fission cross sections of /sup 230/Th, /sup 232/Th, /sup 233/U, /sup 234/U, /sup 236/U, /sup 238/U, /sup 237/Np, /sup 239/Pu and /sup 242/Pu relative /sup 235/U at 14. 74 MeV neutron energy
Technical Report
·
Sun Nov 30 23:00:00 EST 1986
·
OSTI ID:6769505
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ACTINIDES
ALPHA DECAY RADIOISOTOPES
BURNUP
ELEMENTS
EVEN-EVEN NUCLEI
EVEN-ODD NUCLEI
FISSION PRODUCTS
FUEL CYCLE
HEAVY NUCLEI
ISOTOPES
MANAGEMENT
METALS
NUCLEI
POWER REACTORS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE DISPOSAL
RADIOISOTOPES
REACTORS
THORIUM 232
THORIUM ISOTOPES
URANIUM 233
URANIUM ISOTOPES
WASTE DISPOSAL
WASTE MANAGEMENT
YEARS LIVING RADIOISOTOPES
220100* -- Nuclear Reactor Technology-- Theory & Calculation
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ACTINIDES
ALPHA DECAY RADIOISOTOPES
BURNUP
ELEMENTS
EVEN-EVEN NUCLEI
EVEN-ODD NUCLEI
FISSION PRODUCTS
FUEL CYCLE
HEAVY NUCLEI
ISOTOPES
MANAGEMENT
METALS
NUCLEI
POWER REACTORS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE DISPOSAL
RADIOISOTOPES
REACTORS
THORIUM 232
THORIUM ISOTOPES
URANIUM 233
URANIUM ISOTOPES
WASTE DISPOSAL
WASTE MANAGEMENT
YEARS LIVING RADIOISOTOPES