TRIGA fuel burn-up calculations and its confirmation

MCNP-A General Monte Carlo N-Particle Transport Code

Judith F. Briesmeister · 1993 · 5.1K citations

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Developments in gamma scanning irradiated nuclear fuel

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An iterative approach for TRIGA fuel burn-up determination using nondestructive gamma-ray spectrometry

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Engineering, Nuclear Engineering, Analytical Chemistry +15