IRDFF-II: A New Neutron Metrology Library

Trkov, A.; Griffin, Patrick J.; Simakov, S.P.; Greenwood, Lawrence R.; Zolotarev, K. I.; Capote, R.; Aldama, D. Lopez; Chechev, V. P.; Destouches, C.; Kahler, Albert C.; Konno, Chikara; Košťál, Michal; Majerle, M.; Malambu, E.; Ohta, Masao; Pronyaev, V.G.; Radulović, Vladimir; Sato, Shunsuke; Schulc, Martin; Šiméčková, E.; Vavtar, Ingrid; Wagemans, J.; White, Morgan Curtis; Yashima, Hiroshi

doi:10.1016/j.nds.2019.12.001

Cited by 148 publications

(68 citation statements)

References 75 publications

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“…From TENDL-2015, 312 evaluations are adopted in the JEFF-3.3 neutron sublibrary. Of these, 111 are stable nuclides ranging from 17,18 O to 203,205 Tl. This implies that many of the fission product evaluations that were left untouched since JEFF-3.0 are now from TENDL.…”

Section: Discussionmentioning

confidence: 99%

“…32 also demonstrate an improvement in the pre-equilibrium components due to the inclusion of the GDH model. In the figure, the JEFF-3.3 and JEFF-3.2 results are compared with ENDF/B-VIII.0 [180], TENDL-2017 [5] and IRDFF-2 [205]. The JEFF-3.3 evaluation generally compares well to its predecessor and these other evaluations.…”

Section: Zirconiummentioning

confidence: 93%

“…31). The JEFF-3.3 and JEFF-3.2 results are compared with ENDF/B-VIII.0[180], TENDL-2017[5] and IRDFF-2[205].…”

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confidence: 99%

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The joint evaluated fission and fusion nuclear data library, JEFF-3.3

et al. 2020

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The joint evaluated fission and fusion nuclear data library 3.3 is described. New evaluations for neutroninduced interactions with the major actinides 235 U, 238 U and 239 Pu, on 241 Am and 23 Na, 59 Ni, Cr, Cu, Zr, Cd, Hf, W, Au, Pb and Bi are presented. It includes new fission yields, prompt fission neutron spectra and average number of neutrons per fission. In addition, new data for radioactive decay, thermal neutron scattering, gamma-ray emission, neutron activation, delayed neutrons and displacement damage are presented. JEFF-3.3 was complemented by files from the TENDL project. The libraries for photon, proton, deuteron, triton, helion and alpha-particle induced reactions are from TENDL-2017. The demands for uncertainty quantification in modeling led to many new covariance data for the evaluations. A comparison between results from model calculations using the JEFF-3.3 library and those from benchmark experiments for criticality, delayed neutron yields, shielding and decay heat, reveals that JEFF-3.3 performes very well for a wide range of nuclear technology applications, in particular nuclear energy.

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Section: Discussionmentioning

confidence: 99%

Section: Zirconiummentioning

confidence: 93%

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The joint evaluated fission and fusion nuclear data library, JEFF-3.3

et al. 2020

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“…This type of core has been benchmarked [3] in past and the reactivity [4], spatial flux distribution [5], spectrum [6], and power distribution [7] have been characterized. Thus, it acts today as a reference neutron field [8]. Specialty of the benchmark core in the LR-0 reactor is that the criticality is given by the amount of moderator while the control rods are withdrawn to upper position.…”

Section: Lr-0 Reactormentioning

confidence: 99%

Neutron Field Mock-Up Development for the Fluoride Salt Reactors Neutronic Research

et al. 2021

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Experimental work at the LR-0 reactor was carried out to determine the possibility of the mock-up neutron field creation for the fluoride salt-based reactors. Previous calculations and experiments have shown that the fast part of the molten salt reactor (MSR) spectrum is shaped by fluorine and even the Teflon material is suitable for neutronics in that energy range. Properly selected spectrum indices can describe the neutron field of the MSR in fast thermal and intermediate parts of the spectrum. Current research has focused on a deeper study of the possibility of using the filtered thermal and intermediate neutron spectrum of the experimental light water reactor for the physics of fluoride salt-based reactor. LiF-BeF2 (FLIBE) capsule and teflon cylinders are used as a spectrum filters in the LR-0 reactor. Measured results show acceptable C/E-1 agreement in the reaction rates and satisfactory agreement for usage of the FLIBE filtered neutron spectrum determined by the 181Ta(n, γ) monitor as a mock-up in thermal to intermediate energy in the fluoride high-temperature reactor (FHR). Concerning MSR, intermediate spectrum can be reproduced to some extent but not as good as in the case of FHR.

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“…1.0.1 [39,40] were further use to find self-attenuation factor ( Γ attn ) . The 197 Au (n,2n) 196 Au monitor reaction cross section at the neutron energy of 14.54 ± 0.24 MeV was estimated by using a linear interpolation technique, which is 2.1236 ± 0.0205 barns [41,42].…”

Section: Efficiency Calibration Of Hpge Detector With Uncertaintymentioning

confidence: 99%

Measurement of neutron induced reaction cross sections of palladium isotopes at the neutron energy of 14.54 ± 0.24 MeV with covariance analysis

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Suryanarayana

et al. 2020

J Radioanal Nucl Chem

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The 110 Pd(n,2n) 109 Pd, 102 Pd(n,2n) 101 Pd, 105 Pd(n,p) 105 Rh and 106 Pd(n,p) 106m Rh reaction cross sections have been measured with respect to the 197 Au(n,2n) 196 Au monitor reaction at the neutron energy of 14.54 ± 0.24 MeV by using the method of activation and off-line γ-ray spectrometry. The mono-energetic neutron beam was generated from the D-T reaction. The uncertainties in the various basic nuclear parameters in the measured reactions and their correlations were estimated by using covariance analysis. The present data were compared with the EXFOR based literature data, evaluated data of various libraries available in national nuclear data center and with the calculated values from TALYS-1.9 code. Keywords 110 Pd(n,2n) 109 Pd • 102 Pd(n,2n) 101 Pd • 105 Pd(n,p) 105 Rh and 106 Pd(n,p) 106 mRh reactions • D-T reaction neutron source • Activation and off-line γ-ray spectrometry • Covariance analysis • TALYS-1.9

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IRDFF-II: A New Neutron Metrology Library

Cited by 148 publications

References 75 publications

The joint evaluated fission and fusion nuclear data library, JEFF-3.3

The joint evaluated fission and fusion nuclear data library, JEFF-3.3

Neutron Field Mock-Up Development for the Fluoride Salt Reactors Neutronic Research

Measurement of neutron induced reaction cross sections of palladium isotopes at the neutron energy of 14.54 ± 0.24 MeV with covariance analysis

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