Evaluation of Neutron Resonance Cross Section Data at GELINA

Schillebeeckx, P.; Becker, Boris W.; Capote, R.; Emiliani, F.; Guber, K. H.; Heyse, J.; Kauwenberghs, K.; Kopecky, S.; Lampoudis, C.; Massimi, C.; Mondelaers, W.; Moxon, M.C.; Noguère, G.; Plompen, A.; Pronyaev, V.G.; Siegler, P.; Sirakov, I.; Trkov, A.; Volev, K.; Žerovnik, Gašper

doi:10.1016/j.nds.2014.08.027

Cited by 9 publications

(4 citation statements)

References 13 publications

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“…Neutron Energy (MeV) The 89 Y(n,2n) 88 Y reaction cross sections and covariances in energy range up to 20 MeV were evaluated by Zolotarev [83] The plot of the correlation matrix for the 89 Y(n,2n) 88 Y reaction is shown in Fig. 44(a).…”

Section: Neutron Energy (Mev)mentioning

confidence: 99%

“…53(a). The capture cross sections of gold are probably the best known capture cross sections over a broad energy range; this is why they are declared a standard at thermal and in the energy range 0.2 MeV to 2.5 MeV [88]. The ENDF/B-VIII.0 evaluation is consistent with the IAEA Standards 2017 for this reaction, hence it was adopted for IRDFF-II.…”

Section: Hementioning

confidence: 99%

“…The case of 186 W is an interesting one, where we believe the gamma-emission probabilities are mainly responsible for the difference. In the recent re-evaluation of the gamma-emission probabilities the values changed by about 20 %, but the resulting derived thermal capture cross section could not be fitted in a rigorous resonance analysis performed at JRC in Geel [88]. The case of the thermal capture cross section of 186 W remains an open issue.…”

Section: Thermal Reactor Neutron Fields -Thermal Cross Sections and R...mentioning

confidence: 99%

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IRDFF-II: A New Neutron Metrology Library

Trkov,

Griffin,

Simakov

et al. 2019

Preprint

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References 103 TABLE 1: (continued). IRDFF-II nuclear data contents and evaluation sources. (r) denotes renormalization. Consistency v2002 v-1.05 ID Reaction Label MAT Energy Evaluation Eval. to to No. Interval source Date v-1.05 1 IRDFF-II 2 Cross sections of cover materials: Both σtot, σ el and σ abs are tabulated 1 nat B(n,tot) Btot 500 0-20 MeV ENDF/B-VIII.0 2018 old new 20-60 MeV TENDL-2010(r) new 2 10 B(n,tot) B10tot 525 0-20 MeV ENDF/B-VIII.0 2018 old new 20-60 MeV TENDL-2010(r) new 3 nat Cd(n,tot) Cdtot 4800 0-20 MeV JEFF-3.3 2018 old new 20-60 MeV TENDL-2010(r) new 4 nat Gd(n,tot) Gdtot 6400 0-20 MeV ENDF/B-VII.1 [33] 2011 old new 20-60 MeV TENDL-2010(r) new Damage cross sections

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Section: Neutron Energy (Mev)mentioning

confidence: 99%

Section: Hementioning

confidence: 99%

Section: Thermal Reactor Neutron Fields -Thermal Cross Sections and R...mentioning

confidence: 99%

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IRDFF-II: A New Neutron Metrology Library

Trkov,

Griffin,

Simakov

et al. 2019

Preprint

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“…Other neutron timeof-flight facilities comprise electron linac-based machines, like GELINA [19,20], IREN [21], KURRI [22], nELBE [23], ORELA (until recently) [24] and PNF [25], RPI [26], and proton-induced spallation targets similar to n TOF, like MLF at J-PARC [27] and LANSCE [28]. All these facilities have their own unique and often complementary characteristics.…”

Section: Introductionmentioning

confidence: 99%

Nuclear data activities at the n_TOF facility at CERN

et al. 2016

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Abstract. Nuclear data in general, and neutron-induced reaction cross sections in particular, are important for a wide variety of research fields. They play a key role in the safety and criticality assessment of nuclear technology, not only for existing power reactors but also for radiation dosimetry, medical applications, the transmutation of nuclear waste, accelerator-driven systems, fuel cycle investigations and future reactor systems as in Generation IV. Applications of nuclear data are also related to research fields as the study of nuclear level densities and stellar nucleosynthesis. Simulations and calculations of nuclear technology applications largely rely on evaluated nuclear data libraries. The evaluations in these libraries are based both on experimental data and theoretical models. Experimental nuclear reaction data are compiled on a worldwide basis by the international network of Nuclear Reaction Data Centres (NRDC) in the EXFOR database. The EXFOR database forms an important link between nuclear data measurements and the evaluated data libraries. CERN's neutron time-of-flight facility n TOF has produced a considerable amount of experimental data since it has become fully operational with the start of the scientific measurement programme in 2001. While for a long period a single measurement station (EAR1) located at 185 m from the neutron production target was available, the construction of a second beam line at 20 m (EAR2) in 2014 has substantially increased the measurement capabilities of the facility. An outline of the experimental nuclear data activities at CERN's neutron time-of-flight facility n TOF will be presented.

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