scholarly journals Testing JEFF-3.1.1 and ENDF/B-VII.1 Decay and Fission Yield Nuclear Data Libraries with Fission Pulse Neutron Emission and Decay Heat Experiments

2014 ◽  
Vol 118 ◽  
pp. 472-475
Author(s):  
O. Cabellos ◽  
V. de Fusco ◽  
C.J. Diez de la Obra ◽  
J.S. Martinez ◽  
E. Gonzalez ◽  
...  
Keyword(s):  
Neutron Emission ◽  
Nuclear Data ◽  
Pulse Neutron ◽  
Fission Yield ◽  
Decay Heat ◽  
Data Libraries ◽  
Nuclear Data Libraries

scholarly journals Summation calculation of delayed neutron yields for 235U, 238U and 239Pu, based on various fission yield and neutron emission probability databases

2018 ◽  
Vol 193 ◽  
pp. 03004 ◽  
Author(s):  
Daniela Foligno ◽  
Pierre Leconte ◽  
Olivier Serot ◽  
Olivier Litaize ◽  
Abdelhazize Chebboubi
Keyword(s):  
Neutron Yield ◽  
Half Life ◽  
Neutron Emission ◽  
Nuclear Data ◽  
Emission Probability ◽  
Delayed Neutron ◽  
Fission Yield ◽  
Data Libraries ◽  
Nuclear Data Libraries

Summation calculations have been performed in order to compare the quality of several nuclear data libraries. The objective was to obtain the average delayed neutron yield, as well as the average delayed-neutron half-life for different fissioning systems (235U, 238U and 239Pu) at different energies (thermal and fast) by using microscopic data. Each quantity is presented with a first evaluation of the uncertainty, computed under the assumption that the variables are all independent of each other.

scholarly journals A COMPARISON OF OXIDE DECAY HEAT SIMULATIONS AND NUCLEAR DATA LIBRARIES WITH FUSION IRRADIATION EXPERIMENTS

2021 ◽  
Vol 247 ◽  
pp. 09011
Author(s):  
L W Packer ◽  
M Angelone ◽  
M R Gilbert ◽  
S Loreti ◽  
C R Nobs ◽  
...  
Keyword(s):  
Nuclear Data ◽  
Data Sets ◽  
Section Data ◽  
Fusion Neutron ◽  
Decay Heat ◽  
Decay Profile ◽  
Data Points ◽  
Fast Extraction ◽  
Data Libraries ◽  
Nuclear Data Libraries

We compare existing experimental decay heat data sets measured at the JAEA fusion neutron source (FNS), which employed a fast extraction rabbit system that in certain cases allowed the measurements to capture, at short cooling times, the decay profile of 16N in a range of oxides. Focussing on those data points and timescales that can be attributed to 16N, we compare measurements to simulations performed using the FISPACT-II inventory code together with evaluated nuclear data libraries. Making small corrections for other contributions at these short times, we derive integral cross section data estimates for 16O(n,p)16N from 12 oxide sample measurements and compare with previously obtained measurements in the IAEA EXFOR database and evaluations in the nuclear data libraries themselves.

Generation of fission yield covariances to correct discrepancies in the nuclear data libraries

2016 ◽  
Vol 88 ◽  
pp. 12-23 ◽  
Author(s):  
L. Fiorito ◽  
A. Stankovskiy ◽  
G. Van den Eynde ◽  
C.J. Diez ◽  
O. Cabellos ◽  
...  
Keyword(s):  
Nuclear Data ◽  
Fission Yield ◽  
Data Libraries ◽  
Nuclear Data Libraries

Criticality Calculations and Basic Sensitivity/Uncertainty Investigation of LR-0 Benchmark Core

2019 ◽  
Vol 5 (3) ◽  
Author(s):  
Tomáš Czakoj ◽  
Evžen Losa
Keyword(s):  
Lithium Fluoride ◽  
Three Dimensional ◽  
Reactor Core ◽  
Nuclear Data ◽  
Monte Carlo Code ◽  
Multiplication Factor ◽  
Reference Case ◽  
Energy Version ◽  
Data Libraries ◽  
Nuclear Data Libraries

Three-dimensional Monte Carlo code KENO-VI of SCALE-6.2.2 code system was applied for criticality calculation of the LR-0 reactor core. A central module placed in the center of the core was filled by graphite, lithium fluoride-beryllium fluoride (FLIBE), and lithium fluoride-sodium fluoride (FLINA) compounds. The multiplication factor was obtained for all cases using both ENDF/B-VII.0 and ENDF/B-VII.1 nuclear data libraries. Obtained results were compared with benchmark calculations in the MCNP6 using ENDF/B-VII.0 library. The results of KENO-VI calculations are found to be in good agreement with results obtained by the MCNP6. The discrepancies are typically within tens of pcm excluding the case with the FLINA filling. Sensitivities and uncertainties of the reference case with no filling were determined by a continuos-energy version of the TSUNAMI sequence of SCALE-6.2.2. The obtained uncertainty in multiplication factor due to the uncertainties in nuclear data is about 650 pcm with ENDF/B-VII.1.

Sign in / Sign up

Export Citation Format

Share Document