Journal of Nuclear Science and Technology · 1995 · 905 citations · 48 references
EngineeringNuclear EngineeringPhysicsNuclear MaterialsNuclear PhysicsReactor PhysicsCross Section DataNuclear FissionReactor DesignReactor KineticsReactor ModelingFission ReactionsInelastic ScatteringInelastic Scattering Cross SectionsNuclear Data EvaluationReactor SimulationResonance Parameter EvaluationResonance ParametersScattering Cross Sections
The revision work of JENDL-3 has been made by considering feedback information of various benchmark tests. The main revised quantities are the resonance parameters, capture and inelastic scattering cross sections, and fission spectra of main actinide nuclides, the total and inelastic scattering cross sections of structural materials, the resonance parameters the capture and inelastic scattering cross sections of fission products, and the γr-ray production data. The revised data were released as JENDL-3.2 in June 1994. The preliminary benchmark tests indicate that JENDL-3.2 predicts various reactor characteristics more successfully than the previous version of JENDL-3.1.
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MCNP-A General Monte Carlo N-Particle Transport Code
Judith F. Briesmeister · 1993 · 5.1K citations
S.F. Mughabghab, M. Divadeenam, N.E. Holden · 1981 · 928 citations
Direct and semi-direct (p, γ) and (n, γ) reactions
G. E. Brown · Nuclear Physics · 1964 · 233 citations
Multilevel Formula for the Fission Process
C.W. Reich, M. S. Moore · Physical Review · 1958 · 205 citations