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.

scholarly journals EXPERIMENTAL VALIDATION OF NUCLEAR REACTION DATA FOR INVENTORY SIMULATIONS ON MOLYBDENUM

2021 ◽  
Vol 247 ◽  
pp. 09014
Author(s):  
M.R. Gilbert ◽  
L.W. Packer ◽  
T. Stainer
Keyword(s):  
Nuclear Reaction ◽  
Power Plants ◽  
Nuclear Data ◽  
Wall Material ◽  
Fusion Neutron ◽  
Reaction Data ◽  
Radiological Response ◽  
The Uk ◽  
Data Libraries ◽  
Nuclear Data Libraries

Molybdenum is being considered as a potential material for future nuclear fusion experiments and power plants. It has good thermo-mechanical properties and can be easily fabricated, making it attractive as an alternative first wall material to tungsten, which is the current leading candidate. Unfortunately, according to simulations, fusion-neutron irradiated Mo may become too activated during reactor operation to maintain the objective of fusion of avoiding the generation of long-term, higher-level radioactive waste.However, these simulated predictions rely heavily on having high-quality, accurate nuclear reaction data. For example, reliable simulations of the radiological response of isotopically-tailored Mo would be required by reactor designers and eventually nuclear regulators to assess if it is a viable low-activation fusion solution (in comparison to pure Mo). In recent years, UKAEA has developed benchmarks to test and validate the FISPACT-II inventory code and the input international nuclear data libraries against experimental measurements. This paper presents nuclear code prediction comparisons to new data acquired from γ-spectroscopy measurements of Mo irradiated in the ASP 14 MeV facility at AWE in the UK.Results demonstrate that FISPACT-II predictions for Mo are remarkably accurate; particularly for activity generated from the shorter-lived radionuclides explored by these laboratory experiments, such as91Mo and97Nb, etc., and their metastable isomeric states.

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

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.

Sensitivity to Nuclear Data Libraries in the Physics Core Characteristics of Conceptual Thorium Breeders

2011 ◽  
Vol 59 (2(3)) ◽  
pp. 1361-1364
Author(s):  
V. Jagannathan ◽  
U. Pal ◽  
R. Karthikeyan ◽  
A. Srivastava ◽  
S. A. Khan
Keyword(s):  
Nuclear Data ◽  
Data Libraries ◽  
Core Characteristics ◽  
Nuclear Data Libraries
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