ENDF-102 data formats and procedures for the evaluated nuclear data file ENDF-6. Revision November 1995

McLane, V.; Dunford, C.L.; Rose, P.F.

doi:10.2172/270826

Cited by 16 publications

(6 citation statements)

References 3 publications

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“…The thresholds in Table I are obtained from the ENDF-B-VI nuclear database [10]. They correspond to the minimum energy for which the database can provide a reaction cross section.…”

Section: Neutron Nuclear Reactionsmentioning

confidence: 99%

SEU sensitivity of bulk and SOI technologies to 14-MeV neutrons

Gasiot

Ferlet-Cavrois

Baggio

et al. 2002

IEEE Trans. Nucl. Sci.

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This work investigates the effects of 14-MeV neutron irradiation on bulk and silicon-on-insulator (SOI) technologies. Experimental results are reported with a study on the influence of the irradiation angle. These experiments are interpreted with a nuclear interaction code (MCNP: Monte Carlo N-Particle). The device architecture and the involved materials are shown to be determining parameters with respect to the device sensitivity.

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“…The thresholds in Table I are obtained from the ENDF-B-VI nuclear database [10]. They correspond to the minimum energy for which the database can provide a reaction cross section.…”

Section: Neutron Nuclear Reactionsmentioning

confidence: 99%

SEU sensitivity of bulk and SOI technologies to 14-MeV neutrons

Gasiot

Ferlet-Cavrois

Baggio

et al. 2002

IEEE Trans. Nucl. Sci.

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“…The presence of delayed neutrons shifts the behaviour where ϕ α 0 < ϕ k 0 towards 0.6 MeV which is around the average emission energy for delayed neutrons [22]. According to the α-eigenvalue formulation, the delayed fission operator is now rescaled by a factor λ/(λ + α 0 ), with λ = β/∑ j (β j /λ j ) = 0.0768 ± 0.0006 s −1 for U 235 [23]. This factor is still smaller than 1/k 0 , hence ϕ α 0 is still smaller than ϕ k 0 at fast energy range.…”

Section: Problem IIImentioning

confidence: 99%

Comparison of Direct and Adjoint k and α-Eigenfunctions

Vitali

Chevallier

Jinaphanh

et al. 2021

JNE

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Modal expansions based on k-eigenvalues and α-eigenvalues are commonly used in order to investigate the reactor behaviour, each with a distinct point of view: the former is related to fission generations, whereas the latter is related to time. Well-known Monte Carlo methods exist to compute the direct k or α fundamental eigenmodes, based on variants of the power iteration. The possibility of computing adjoint eigenfunctions in continuous-energy transport has been recently implemented and tested in the development version of TRIPOLI-4®, using a modified version of the Iterated Fission Probability (IFP) method for the adjoint α calculation. In this work we present a preliminary comparison of direct and adjoint k and α eigenmodes by Monte Carlo methods, for small deviations from criticality. When the reactor is exactly critical, i.e., for k0 = 1 or equivalently α0 = 0, the fundamental modes of both eigenfunction bases coincide, as expected on physical grounds. However, for non-critical systems the fundamental k and α eigenmodes show significant discrepancies.

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“…This system includes the widely-used NJOY code [MacFarlane, et al, 1982] for processing ENDF nuclear data files [McLane, et al, 1990]. The exceptions are the probability tables for treating the unresolved resonance range (URR), which are generated from the ENDF/B data by other codes; and the data used for the continuous-energy thermal range treatment, which is obtained by the RACER system directly from the ENDF/Et files.…”

Section: Nuclear Datamentioning

confidence: 99%

“…The number of bins used to describe the thermal supergroup is specified by the user, with 1000 being a typical value. Three scattering law formalisms [McLane, 1990] are used to treat the three major scattering mechanisms in the thermal range: i.e., incoherent inelastic, coherent elastic, and incoherent elastic. Each of these will be described in turn.…”

Section: Continuous Energy Thermal-range Physicsmentioning

confidence: 99%