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J.R. Granada

Researcher at Balseiro Institute

Publications -  96
Citations -  1607

J.R. Granada is an academic researcher from Balseiro Institute. The author has contributed to research in topics: Neutron & Neutron scattering. The author has an hindex of 20, co-authored 95 publications receiving 1344 citations. Previous affiliations of J.R. Granada include National Atomic Energy Commission & National University of Cuyo.

Papers
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Journal ArticleDOI

The joint evaluated fission and fusion nuclear data library, JEFF-3.3

A. J. M. Plompen, +79 more
TL;DR: The JEFF-3.3 data library as mentioned in this paper is a joint evaluated fission and fusion nuclear data library 3.3 which includes new fission yields, prompt fission neutron spectra and average number of neutrons per fission.
Book ChapterDOI

Neutron Scattering Lengths and Cross Sections

TL;DR: In this paper, an updated table of neutron scattering lengths and cross sections for most of the known nuclides, based on preexisting works, is presented, including the coherent and incoherent scattering lengths, as well as the spin-dependent scattering lengths b + and b −, in cases where this information is available.
Journal ArticleDOI

Slow-neutron scattering by molecular gases: A synthetic scattering function.

J.R. Granada
- 01 Apr 1985 - 
TL;DR: Les principales caracteristiques de the dynamique moleculaire sont prises en compte par l'introduction d'une masse effective, and de facteurs de temperature and de vibration qui dependent of l'energie E 0 des neutrons incidents.
Journal ArticleDOI

CAB models for water: A new evaluation of the thermal neutron scattering laws for light and heavy water in ENDF-6 format

TL;DR: In this paper, a set of new models for the evaluation of thermal neutron scattering laws for light and heavy water in ENDF-6 format, using the LEAPR module of NJOY, were presented.
Journal ArticleDOI

Calculation of neutron cross sections and thermalization parameters for molecular gases using a synthetic scattering function. II. Applications to H2O, D2O, and C6H6.

TL;DR: Within the framework of neutron diffusion theory, transport coefficients are readily evaluated using the model expressions and they are compared with available information over a wide range of temperatures.