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NSR database version of April 25, 2024.

Search: Author = C.J.Diez

Found 9 matches.

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2017RO02      Nucl.Data Sheets 139, 1 (2017)

D.Rochman, O.Leray, M.Hursin, H.Ferroukhi, A.Vasiliev, A.Aures, F.Bostelmann, W.Zwermann, O.Cabellos, C.J.Diez, J.Dyrda, N.Garcia-Herranz, E.Castro, S.van der Marck, H.Sjostrand, A.Hernandez, M.Fleming, J.-Ch.Sublet, L.Fiorito

Nuclear Data Uncertainties for Typical LWR Fuel Assemblies and a Simple Reactor Core

doi: 10.1016/j.nds.2017.01.001
Citations: PlumX Metrics

2016FI02      Ann.Nucl.Energy 88, 12 (2016)

L.Fiorito, A.Stankovskiy, G.Van den Eynde, C.J.Diez, O.Cabellos, P.E.Labeau

Generation of fission yield covariances to correct discrepancies in the nuclear data libraries

NUCLEAR REACTIONS ²³²Th, ^233,235,238U, ^239,241Pu(n, F), E=0.0000000253, 0.4, 14 MeV; calculated covariance matrices; deduced JEFF-3.1.1 library discrepancies. Comparison with available data.

doi: 10.1016/j.anucene.2015.10.027
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2015DI01      Nucl.Data Sheets 123, 79 (2015)

C.J.Diez, O.Cabellos, J.S.Martinez

Nuclear Data Uncertainty Propagation in Depletion Calculations Using Cross Section Uncertainties in One-group or Multi-group

doi: 10.1016/j.nds.2014.12.014
Citations: PlumX Metrics

2014DI12      Nucl.Data Sheets 118, 516 (2014)

C.J.Diez, O.Cabellos, J.S.Martinez, A.Stankovskiy, G.Van den Eynde, P.Schillebeeckx, J.Heyse

Analysis of ²³⁸Pu and ⁵⁶Fe Evaluated Data for Use in MYRRHA

doi: 10.1016/j.nds.2014.04.122
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2014DI13      Nucl.Data Sheets 118, 538 (2014)

C.J.Diez, O.Cabellos, J.S.Martinez

Impact of Nuclear Data Uncertainties on Advanced Fuel Cycles and their Irradiated Fuel - Comparison between Libraries

COMPILATION ^93m,94Nb, ⁹³Mo, ¹⁰³Rh, ¹⁰⁷Pd, ¹⁰⁹Ag, ¹²⁶Sn, ^126,126mSb, ¹²⁹I, ^{149,150,151,152}Sm, ^151,153Eu, ¹⁵⁵Gd, ^235,238U, ²³⁷Np, ^{238,239,240,241,242}Pu, ^241,242m,243Am, ^{242,243,244,245,246,247}Cm, ²⁴⁹Bk, ²⁵²Cf; compiled, calculated burn-up yields uncertainties, σ uncertainties using ACAB code. Compared different data libraries.

doi: 10.1016/j.nds.2014.04.128
Citations: PlumX Metrics

2014FI06      Ann.Nucl.Energy 69, 331 (2014)

L.Fiorito, C.J.Diez, O.Cabellos, A.Stankovskiy, G.Van den Eynde, P.E.Labeau

Fission yield covariance generation and uncertainty propagation through fission pulse decay heat calculation

NUCLEAR REACTIONS ²³⁵U(n, F)⁸⁸Br/⁸⁸Kr/⁸⁹Kr/⁹⁰Kr/⁹¹Kr/⁹²Kr/⁹²Rb/⁹³Rb/⁹⁵Rb/⁹⁴Sr/⁹⁵Sr/⁹⁶Sr/⁹⁷Sr/⁹⁷Y/⁹⁸Y/⁹⁹Y/⁹⁹Zr/¹⁰⁰Zr/¹⁰¹Zr/¹⁰²Zr/¹³²Sb/¹³³Sb/¹³²Te/¹³³Te/¹³⁴Te/¹³⁵Te/¹³⁶Te/¹³⁵I/¹³⁸I/¹³⁸Xe/¹³⁹Xe/¹⁴⁰Xe/¹⁴⁰Cs/¹⁴²Cs/¹⁴²Ba/¹⁴³Ba/¹⁴⁴Ba, E thermal; calculated fission product yield covariances and uncertainties. ACAB and ALEPH-2 libraries and codes.

doi: 10.1016/j.anucene.2014.01.038
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2014HE22      Nucl.Data Sheets 118, 535 (2014)

J.J.Herrero, R.Ochoa, J.S.Martinez, C.J.Diez, N.Garcia-Herranz, O.Cabellos

Nuclear Data Uncertainty Propagation to Reactivity Coefficients of a Sodium Fast Reactor

doi: 10.1016/j.nds.2014.04.127
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2014ST21      Nucl.Data Sheets 118, 513 (2014)

A.Stankovskiy, E.Malambu, G.Van den Eynde, C.J.Diez

Nuclear Data Needs for the Neutronic Design of MYRRHA Fast Spectrum Research Reactor

doi: 10.1016/j.nds.2014.04.121
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2013DI12      Ann.Nucl.Energy 60, 210 (2013)

C.J.Diez, A.Stankovskiy, E.Malambu, G.Zerovnik, P.Schillebeeckx, G.Van den Eynde, J.Heyse, O.Cabellos

Review of the ^natC(n, γ) cross section and criticality calculations of the graphite moderated reactor BR1

NUCLEAR REACTIONS C, ¹²C(n, γ), E<20 MeV; analyzed available data; deduced recommended σ, k_eff. Comparison with ENDF/B-VII.1, JENDL-4.0 evaluated libraries and EXFOR experimental library.

doi: 10.1016/j.anucene.2013.05.003
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