High accuracy 234U(n,f) cross section in the resonance energy region
Leal-Cidoncha, E., Durán, I., Paradela, C., Tassan-Got, L., Audouin, L., Leal, L. C., Naour, C. Le, Noguere, G., Tarrío, D., Leong, L. S., Altstadt, S., Andrzejewski, J., Barbagallo, M., Bécares, V., Bečvář, F., Belloni, F., Berthoumieux, E., Billowes, J., Boccone, V., Bosnar, D., Brugger, M., Calviani, M., Calviño, F., Cano-Ott, D., Carrapiço, C., Cerutti, F., Chiaveri, E., Chin, M., Colonna, N., Cortés, G., Cortés-Giraldo, M. A., Diakaki, M., Domingo-Pardo, C., Dressler, R., Eleftheriadis, C., Ferrari, A., Fraval, K., Ganesan, S., García, A. R., Giubrone, G., Gómez-Hornillos, M. B., Gonçalves, I. F., González-Romero, E., Griesmayer, E., Guerrero, C., Gunsing, F., Gurusamy, P., Hernández-Prieto, A., Jenkins, D. G., Jericha, E., Kadi, Y., Käppeler, F., Karadimos, D., Kivel, N., Kokkoris, M., Krtička, M., Kroll, J., Lampoudis, C., Langer, C., Lederer, C., Leeb, H., Losito, R., Mallick, A., Manousos, A., Marganiec, J., Martínez, T., Massimi, C., Mastinu, P. F., Mastromarco, M., Meaze, M., Mendoza, E., Mengoni, A., Milazzo, P. M., Mingrone, F., Mirea, M., Mondelaers, W., Pavlik, A., Perkowski, J., Plompen, A., Praena, J., Quesada, J. M., Rauscher, T., Reifarth, R., Riego, A., Robles, M. S., Roman, F., Rubbia, C, Sabaté-Gilarte, M., Sarmento, R., Saxena, A., Schillebeeckx, P., Schmidt, S., Schumann, D., Tagliente, G., Tain, J. L., Tsinganis, A., Valenta, S., Vannini, G., Variale, V., Vaz, P., Ventura, A., Versaci, R., Vermeulen, M. J., Vlachoudis, V., Vlastou, R., Wallner, A., Ware, T., Weigand, M., Weiß, C., Wright, T. and Ugec, P.
(2017)
High accuracy 234U(n,f) cross section in the resonance energy region.
In:
ND 2016: International Conference on Nuclear Data for Science and Technology :.
EDP Sciences, BEL.
ISBN 9782759890200
New results are presented of the 234U neutron-induced fission cross section, obtained with high accuracy in the resonance region by means of two methods using the 235U(n,f) as reference. The recent evaluation of the 235U(n,f) obtained with SAMMY by L. C. Leal et al. (these Proceedings), based on previous n-TOF data [1], has been used to calculate the 234U(n,f) cross section through the 234U/235U ratio, being here compared with the results obtained by using the n-TOF neutron flux.
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