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
- Journal Information:
- Natl. Bur. Stand. (U.S.), Spec. Publ.; (United States), Vol. 1; Conference: Proceedings on nuclear cross section and technology, Washington, DC, USA, 3 Mar 1975; Other Information: See NBS-SPEC.PUBL.--425(Vol. 1); CONF-750303--P1
- Country of Publication:
- United States
- Language:
- English
Similar Records
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
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
NEUTRON-INDUCED FISSION CROSS SECTIONS OF Th*SUP 232/ AND U*SUP 238/ IN THE ENERGY RANGE OF 3 TO 11 Mev. NEUTRON-INDUCED FISSION CROSS SECTIONS OF U*SUP 233/, U*SUP 235/, Np*SUP 237/, AND Pu*SUP 239/ IN THE ENERGY RANGE OF 3 TO 8 Mev
Technical Report
·
Mon Dec 01 00:00:00 EST 1986
·
OSTI ID:7290992
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
Journal Article
·
Tue Dec 01 00:00:00 EST 1981
· Sov. J. Nucl. Phys. (Engl. Transl.); (United States)
·
OSTI ID:7290992
+6 more
NEUTRON-INDUCED FISSION CROSS SECTIONS OF Th*SUP 232/ AND U*SUP 238/ IN THE ENERGY RANGE OF 3 TO 11 Mev. NEUTRON-INDUCED FISSION CROSS SECTIONS OF U*SUP 233/, U*SUP 235/, Np*SUP 237/, AND Pu*SUP 239/ IN THE ENERGY RANGE OF 3 TO 8 Mev
Technical Report
·
Sat Oct 31 00:00:00 EST 1959
·
OSTI ID:7290992
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
ACTINIDES
BURNUP
POWER REACTORS
FUEL CYCLE
FISSION PRODUCTS
RADIOACTIVE WASTE DISPOSAL
THORIUM 232
URANIUM 233
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
ELEMENTS
EVEN-EVEN NUCLEI
EVEN-ODD NUCLEI
HEAVY NUCLEI
ISOTOPES
MANAGEMENT
METALS
NUCLEI
RADIOACTIVE MATERIALS
RADIOISOTOPES
REACTORS
THORIUM ISOTOPES
URANIUM ISOTOPES
WASTE DISPOSAL
WASTE MANAGEMENT
YEARS LIVING RADIOISOTOPES
220100* - Nuclear Reactor Technology- Theory & Calculation
ACTINIDES
BURNUP
POWER REACTORS
FUEL CYCLE
FISSION PRODUCTS
RADIOACTIVE WASTE DISPOSAL
THORIUM 232
URANIUM 233
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
ELEMENTS
EVEN-EVEN NUCLEI
EVEN-ODD NUCLEI
HEAVY NUCLEI
ISOTOPES
MANAGEMENT
METALS
NUCLEI
RADIOACTIVE MATERIALS
RADIOISOTOPES
REACTORS
THORIUM ISOTOPES
URANIUM ISOTOPES
WASTE DISPOSAL
WASTE MANAGEMENT
YEARS LIVING RADIOISOTOPES
220100* - Nuclear Reactor Technology- Theory & Calculation