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Author  |
n_TOF Collaboration (Cano-Ott, D. et al); Domingo-Pardo, C.; Tain, J.L. |
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Title |
Neutron Capture Measuremetns on Minor Actinides at the n_TOF Facility at CERN: Past, Present and Future |
Type |
Journal Article |
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Year |
2011 |
Publication |
Journal of the Korean Physical Society |
Abbreviated Journal |
J. Korean Phys. Soc. |
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Volume |
59 |
Issue |
2 |
Pages |
1809-1812 |
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Keywords |
n_TOF; Total Absorption Calorimeter; TAC; Neutron capture; Cross section; Nuclear waste; Transmutation; Generation IV; Accelerator driven system; ADS; Nuclear reactor; Nuclear energy; Nuclear data; Barium fluoride; Actinides; Plutonium; Americium; Uranium |
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Abstract |
The successful development of advanced nuclear systems for sustainable energy production and nuclear waste management depends on high quality nuclear data libraries. Recent sensitivity studies and reports [1-3] have identified the need for substantially improving the accuracy of neutron cross-section data for minor actinides. The n_TOF collaboration has initiated an ambitious experimental program for the measurement of neutron capture cross sections of minor actinides. Two experimental setups have been constructed for this purpose: a Total Absorption Calorimeter (TAC) [4] for measuring neutron capture cross-sections of low-mass and/or radioactive samples and a set of two low neutron sensitivity C(6)D(6) detectors for the less radioactive materials. |
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Address |
[Cano-Ott, D; Alvarez-Velarde, F; Gonzalez-Romero, E; Guerrero, C; Martinez, T; Mendoza, E; Villamarin, D; Vicente, MC] Ctr Invest Energet Medioambientales & Technol CIE, Madrid, Spain, Email: daniel.cano@ciemat.es |
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Publisher |
Korean Physical Soc |
Place of Publication |
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Language |
English |
Summary Language |
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Original Title |
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Series Editor |
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Series Title |
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Abbreviated Series Title |
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Series Volume |
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Series Issue |
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Edition |
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ISSN |
0374-4884 |
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Conference |
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Notes |
WOS:000294080700085 |
Approved |
no |
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Is ISI |
yes |
International Collaboration |
yes |
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Call Number |
IFIC @ elepoucu @ |
Serial |
737 |
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Author |
Romero-Barrientos, J.; Marquez Damian, J.I.; Molina, F.; Zambra, M.; Aguilera, P.; Lopez-Usquiano, F.; Parra, B.; Ruiz, A. |
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Title |
Calculation of kinetic parameters beta eff and L with modified open source Monte Carlo code OpenMC(TD) |
Type |
Journal Article |
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Year |
2022 |
Publication |
Nuclear Engineering and Technology |
Abbreviated Journal |
Nucl. Eng. Technol. |
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Volume |
54 |
Issue |
3 |
Pages |
811-816 |
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Keywords |
OpenMC; Monte Carlo; Kinetic parameters; Open source; Neutron generation time; Effective delayed neutron fraction |
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Abstract |
This work presents the methodology used to expand the capabilities of the Monte Carlo code OpenMC for the calculation of reactor kinetic parameters: effective delayed neutron fraction beff and neutron generation time L. The modified code, OpenMC(Time-Dependent) or OpenMC(TD), was then used to calculate the effective delayed neutron fraction by using the prompt method, while the neutron generation time was estimated using the pulsed method, fitting L to the decay of the neutron population. OpenMC(TD) is intended to serve as an alternative for the estimation of kinetic parameters when licensed codes are not available. The results obtained are compared to experimental data and MCNP calculated values for 18 benchmark configurations. |
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Address |
[Romero-Barrientos, J.; Molina, F.; Zambra, M.; Aguilera, P.; Lopez-Usquiano, F.; Ruiz, A.] Comis Chilena Energia Nucl, Santiago 12501, Chile, Email: romeroj@uchile.cl |
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Corporate Author |
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Thesis |
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Publisher |
Korean Nuclear Soc |
Place of Publication |
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Editor |
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Language |
English |
Summary Language |
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Original Title |
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Series Editor |
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Series Title |
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Abbreviated Series Title |
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Series Volume |
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Series Issue |
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Edition |
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ISSN |
1738-5733 |
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Conference |
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Notes |
WOS:000766649800004 |
Approved |
no |
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Is ISI |
yes |
International Collaboration |
yes |
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Call Number |
IFIC @ pastor @ |
Serial |
5172 |
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