ENDF/B-VI
Sensitivity and Uncertainty Analysis of the Keff Due to ENDF/B VII 0 Cross Sections Uncertainties of the Major Isotopes in Nuclear Reactors
... Several sensitivities and uncertainties analysis for improving and adjusting the cross sections of the important isotopes in nuclear data evaluation ENDF/B-VII.0 and in simple and complex nuclear systems ...
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ENDF/B VII 0, JEFF 3 1 and JENDL 4 Iron and Water Cross Sections Analysis Using the PCA REPLICA Shielding
... ENDF/B-VII.0[2], JEFF-3.1[3] and JENDL-4[4].These isotopes where chosen because they are considered as major components for constituting the shielding structural . For this analysis, a 3-D model of the ...
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Processing and validation of JEFF-3.1.1 and ENDF/B-VII.0 group-wise cross section libraries for shielding calculations
... Abstract. This paper presents a synthesis of the ENEA-Bologna Nuclear Data Group programme dedicated to generate and validate group-wise cross section libraries for shielding and radiation damage deterministic ...
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Monte carlo interpretation of shielding benchmark experiment nesdip and analysis of endf/b vii 0, jeff 3 1 and jendl 4 iron and water cross sections
... throw the interpretation of the NESDIP benchmark experiment. These isotopes where chosen because they are considered as major elements for constituting the shielding structural components. For this interpretation, a 3-D ...
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High accuracy 235U(n,f) data in the resonance energy region
... U neutron-induced cross section is widely used as reference cross section for measuring other fission cross sections, but in the resonance region it is not considered as an IAEA standard because of the scarce ...
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Sensitivity and Uncertainty Analysis on the Keff Produced by the 1H, 16O, 239Pu and 240Pu Cross Sections Uncertainties
... Carlo codes developing capabilities of computing eigenvalue sensitivity coefficients with regard to nuclear data, including MONK , Mc CARD, MCNP6 ,the continuous-energy version of TSUNAMI-3D in SCALE 6.2 ,RMC, SERPENT ...
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Need of a consistent and convenient nucleus identification in ENDF files for the automatic construction of the depletion chains
... The coherence between decay and FPY evaluations is practically guaranteed by the fact that one needs the information contained in decay in order to calculate the evaluated cumulative fission prod- uct yields (MF = 8,MT = ...
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Evaluation of Geometric Progression (GP) Buildup Factors using MCNP Codes (MCNP6.1 and MCNP5-1.60)
... Abstract. The gamma-ray buildup factors of three-dimensional point kernel code (QAD- CGGP) are re-evaluated by using MCNP codes (MCNP6.1 and MCNPX5-1.60) and ENDF/B-VI.8 photoatomic data, which cover ...
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Criticality experiments and benchmarks for cross section evaluation: the neptunium case
... This seemingly singular behavior might shed some doubt on the level of accuracy of the n_TOF results. However, one should be aware that several of the previous results are not independent because they have been ...
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Calculation of Beta Decay Half-Lives and Delayed Neutron Branching Ratio of Fission Fragments with Skyrme-QRPA
... To calculate β-decay and DN, we have developed a new approach, which comprises quasiparticle- random-phase-approximation (QRPA) and the Hauser-Feshbach statistical model (HFSM) [8]. This approach is capable to calculate ...
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GALILÉE-1: a validation and processing system for ENDF-6 and GND evaluations
... Angular distribution of emitted particles can be represented by Legendre polynomial expansion coefficients. This representation is particularly efficient in terms of compactness. However, the truncation at a given order ...
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Evaluating the 239Pu Prompt Fission Neutron Spectrum Induced by Thermal to 30 MeV Neutrons
... in the lower panels of Fig. 1 due to the improvements made in the model description. In ENDF/B- VII.1, all neutrons evaporated from the initial and subsequent compound nuclei are counted, while in the ...
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Summation calculation of delayed neutron yields for 235U, 238U and 239Pu, based on various fission yield and neutron emission probability databases
... Indeed, this precursor contributes to 10% of the ν d according to ENDF / B-VII.0 and to 1% according to ENDF / B-VII.1 because, in the most recent version of the library, the metastable [r] ...
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Production and testing of the ENEA-Bologna VITJEFF32.BOLIB (JEFF-3.2) multi-group (199 n + 42 γ) cross section library in AMPX format for nuclear fission applications
... Abstract. The ENEA-Bologna Nuclear Data Group produced the VITJEFF32.BOLIB multi-group coupled neutron/photon (199 n + 42 J ) cross section library in AMPX format, based on the OECD-NEA Data Bank JEFF-3.2 evaluated ...
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Propagation of nuclear data uncertainty: Exact or with covariances
... Since the beginning of the century, the nuclear data evaluation community is putting more and more attention to the assessment of uncertainties. This increased interest concerns both basic data (cross sections, emission ...
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Validation of Neutron Evaluated Data Based on The Experimental Reactivity Worth of Tungsten Target in CiADS
... The reactivity worth value of tungsten cylindrical target has been measured as -1.234±0.114mk by period method on VENUS-II light water reactor at China Institute of Atomic Energy. Meanwhile, the MCNP simulations were ...
5
Hepatitis B Screening and Evaluation of Hepatitis B Vaccination Status Among Medical Staff at Med VI University Hospital of Marrakech (CHU)
... hepatitis B virus is a care-associated infection and nosocomial; the doctor may be exposed but perhaps the ...hepatitis B vaccination and the reinforcement of universal hygiene precautions, and occurred ...
5
Experiments with Toroidal Microresonators in Cavity QED
... taper-toroid separation, the laser must first be locked to the toroid resonance. This has been accomplished, at least in preliminary form, by using the error signal used in the characterization of toroids (Chapter 4) as ...
175
Interface Recombination & Emission Applied to Explain Photosynthetic Mechanisms for (e–, h+) Charges’ Separation
... Photosynthetic’ natural light reactions are represented by energy bands of different molecules that absorb light and transfer its energy to others molecules. This energetic representation is called “ground state energy” ...
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Hydrogen sulfide and organic compounds removal in municipal wastewater using ferrate (VI) and ultraviolet radiation
... of 23.5, 45, 60, 70 and 80°C for 15 minutes. Given that the increase in temperature may cause evaporation of volatile organic compounds in wastewater, each Erlenmeyer flasks was considered as a control sample. Finally, ...
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