Measurement of the /sup 235/U neutron-induced fission cross section at 14. 1 MeV

Journal Article · Mon Feb 01 04:00:00 EST 1982 · Nucl. Sci. Eng.; (United States)

OSTI ID:5087736

Wasson, O A; Carlson, A D

The /sup 235/U neutron-induced fission cross section was measured at a neutron energy of 14.1 MeV using the time-correlated associated-particle technique with the /sup 3/H(d,..cap alpha..)n reaction at the National Bureau of Standards 3-MV Van de Graaff Laboratory. The areal density and total mass of the /sup 235/U deposits were measured relative to the standard /sup 235/U reference deposit (Los Alamos National Laboratory Spare Number 1) using thermal-neutron-induced fission counting. The total mass was also determined from the alpha-particle decay rate. The measured /sup 235/U cross section at 14.1 + or - 0.1 MeV is 2.080 + or - 0.030 b where the uncertainty i one standard deviation. This value agrees within 1% with other recent measurements using this technique and with the ENDF/B-V evaluation.

• Research Organization: National Bureau of Standards, Washington, DC
• OSTI ID: 5087736
• Journal Information: Nucl. Sci. Eng.; (United States), Journal Name: Nucl. Sci. Eng.; (United States) Vol. 80:2; ISSN NSENA
• Country of Publication: United States
• Language: English

Related Subjects

652025* -- Nuclear Properties & Reactions
A=220 & above
Experimental-- Nuclear Reactions & Scattering-- (-1987)
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
ALPHA DECAY
BARYON REACTIONS
BARYONS
CHARGED-PARTICLE REACTIONS
COMPUTER CALCULATIONS
COMPUTER CODES
CROSS SECTIONS
DECAY
DEUTERON REACTIONS
E CODES
ELEMENTARY PARTICLES
ENERGY RANGE
FERMIONS
FISSION
HADRON REACTIONS
HADRONS
HELIUM 3 TARGET
MEASURING METHODS
MEV RANGE
MEV RANGE 10-100
NEUTRON REACTIONS
NEUTRONS
NUCLEAR REACTIONS
NUCLEON REACTIONS
NUCLEONS
TARGETS
THERMAL FISSION
THERMAL NEUTRONS
URANIUM 235 TARGET