Pellet ad pellet-blanket neutronics and photonics for electron beam fusion
Journal Article
·
· Nucl. Technol.; (United States)
OSTI ID:5478208
- Univ. of Illinois, Urbana
Pellet and coupled pellet-blanket time-integrated neutronics and photonics calculations are reported for a representative low-gain (25), low-compression (deuterium-tritium core pr = 9.4 kg/m/sup 2/) pellet design for an electron beam fusion reactor. Tungsten, lead, and natural uranium are compared as pusher-tamper materials. In the three cases, neutron balances show that neutron multiplication in the pellet compensates for the energy losses and spectral softening due to neutron interactions. Fissile breeding cannot be achieved in the natural uranium case, since the fission reaction predominates. Substantive additonal energy can be obtained (approx. 5.5 MeV/source neutron) in the pellet if natural uranium is used as the tamper material. Neutron and gamma spectra from the pellet microexplosions are given.
- OSTI ID:
- 5478208
- Journal Information:
- Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 48:1; ISSN NUTYB
- Country of Publication:
- United States
- Language:
- English
Similar Records
Fission-suppressed blankets for fissile fuel breeding fusion reactors
/sup 233/U breeding and neutron multiplying blankets for fusion reactors
Molten salt blanket calculations for a tokamak fusion-fission hybrid reactor
Journal Article
·
Wed Jul 01 00:00:00 EDT 1981
· J. Fusion Energy; (United States)
·
OSTI ID:5136749
/sup 233/U breeding and neutron multiplying blankets for fusion reactors
Journal Article
·
Thu Jul 01 00:00:00 EDT 1976
· Nucl. Technol.; (United States)
·
OSTI ID:7241468
Molten salt blanket calculations for a tokamak fusion-fission hybrid reactor
Technical Report
·
Wed Mar 31 23:00:00 EST 1976
·
OSTI ID:7348608
Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700208* -- Fusion Power Plant Technology-- Inertial Confinement Technology
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALKALI METAL ISOTOPES
ALPHA DECAY RADIOISOTOPES
BARYON REACTIONS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BREEDING
BREEDING BLANKETS
DEUTERIUM COMPOUNDS
DEUTERIUM TRITIDES
E-BEAM TYPE REACTORS
ELECTRON BEAM TARGETS
ELEMENTS
EVEN-EVEN NUCLEI
FUEL PELLETS
GAMMA SPECTRA
HADRON REACTIONS
HEAVY NUCLEI
HYDROGEN COMPOUNDS
HYDROGEN ISOTOPES
ISOTOPES
LABELLED COMPOUNDS
LEAD
LIGHT NUCLEI
LITHIUM 6
LITHIUM 7
LITHIUM ISOTOPES
METALS
NEUTRON REACTIONS
NEUTRON SPECTRA
NUCLEAR FUEL CONVERSION
NUCLEAR REACTIONS
NUCLEI
NUCLEON REACTIONS
ODD-EVEN NUCLEI
ODD-ODD NUCLEI
PELLETS
RADIOISOTOPES
REACTOR COMPONENTS
REFRACTORY METALS
SPECTRA
STABLE ISOTOPES
TARGETS
THERMONUCLEAR REACTORS
TRANSITION ELEMENTS
TRITIUM
TRITIUM COMPOUNDS
TUNGSTEN
URANIUM 238
URANIUM ISOTOPES
YEARS LIVING RADIOISOTOPES
700208* -- Fusion Power Plant Technology-- Inertial Confinement Technology
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALKALI METAL ISOTOPES
ALPHA DECAY RADIOISOTOPES
BARYON REACTIONS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BREEDING
BREEDING BLANKETS
DEUTERIUM COMPOUNDS
DEUTERIUM TRITIDES
E-BEAM TYPE REACTORS
ELECTRON BEAM TARGETS
ELEMENTS
EVEN-EVEN NUCLEI
FUEL PELLETS
GAMMA SPECTRA
HADRON REACTIONS
HEAVY NUCLEI
HYDROGEN COMPOUNDS
HYDROGEN ISOTOPES
ISOTOPES
LABELLED COMPOUNDS
LEAD
LIGHT NUCLEI
LITHIUM 6
LITHIUM 7
LITHIUM ISOTOPES
METALS
NEUTRON REACTIONS
NEUTRON SPECTRA
NUCLEAR FUEL CONVERSION
NUCLEAR REACTIONS
NUCLEI
NUCLEON REACTIONS
ODD-EVEN NUCLEI
ODD-ODD NUCLEI
PELLETS
RADIOISOTOPES
REACTOR COMPONENTS
REFRACTORY METALS
SPECTRA
STABLE ISOTOPES
TARGETS
THERMONUCLEAR REACTORS
TRANSITION ELEMENTS
TRITIUM
TRITIUM COMPOUNDS
TUNGSTEN
URANIUM 238
URANIUM ISOTOPES
YEARS LIVING RADIOISOTOPES