The purpose of the project entitled Compilation of Nuclear Data Experiments for Radiation Characterisation (CoNDERC) is to transfer into technology the experimental integral radiation information that can be used as part of the Validation and Verification processes of nuclear model and code systems, and to provide various schemas to perform the necessary V&V protocols. The IAEA coordinate,...
Short presentation explaining the workflow of ingesting and disseminating data on the new CoNDERC website. The presentation will include possible future developments using GitHub for collecting and releasing data sets.
The international SINBAD, ICSBEP, IRPhE, and SFCOMPO projects under the auspices of the Nuclear Science Committee (NSC) of the OECD Nuclear Energy Agency (NEA) provide integral benchmarks to improve nuclear data evaluations and serve as cornerstones in the verification and validation (V&V) process of radiation transport simulations. Experts from OECD NEA member countries, and beyond,...
In the last couple of years, a combined effort between NIER, Università di Bologna and Fusion For Energy led to the development of JADE, a python-based open-source software for the Verification and Validation of nuclear data libraries. Nuclear data is fundamental for particle and radiation transport simulations which, in turn, are responsible for the evaluation of key quantities for...
The paper presents results from neutron flux calculations in the DEMO divertor region in the case of the Helium Cooled Pebble Bed (HCPB) concept used as a breeding blanket (BB) option. Calculations were performed with support by ADVANTG (AutomateD VAriaNce reducTion Generator) with FW-CADIS variance reduction parameters tool used for the variance reduction purposes. Such coupled computational...
This talk gives an overview of the development and applications of Serpent at VTT Technical research centre of Finland Ltd focusing on the nuclear and atomic data needs of Serpent as well as the validation of Serpent at VTT.
Serpent transports neutrons and photons in a decoupled or coupled manner starting from a criticality source, a fixed source or a radioactive decay source. Serpent is...
A number of benchmark compilations have been developed in recent years that are utilized by nuclear data testers worldwide. These include Handbooks from the International Criticality Safety Benchmark Evaluation Project (ICSBEP), and the International Reactor Physics Evaluation Project (IRPhEP), as well as the Shielding Integral Benchmark Archive Database (SINBAD) and the Spent Fuel Isotopic...
This talk will give a broad overview of the verification and validation activities being performed using the OpenMC particle transport code. The OpenMC community has relied extensively on benchmark models from the ICSBEP handbook for both cross-code comparisons and comparison to experiment. To date, about 400 different benchmark models from ICSBEP have been created with OpenMC. Along with...
This work follows the MCNP - TRIPOLI-4 comparisons for criticality benchmarks using U5, U8, Pu9, for which comparisons were made between ENDF/B-VIII, JEFF-3.3, TENDL-17, TENDL-19 libraries. The study of shielding benchmarks shows differences between the libraries for different nuclei and indicates the importance of the scattering anisotropy. The new Fe56 evaluation of TENDL-21 provides a...
The Nuclear Criticality Safety Division at Lawrence Livermore National Laboratory is developing an extended suite of validation benchmarks for its Monte Carlo code COG. The benchmarks serve to validate nuclear data and to support COG's software quality assurance framework. The current database has 3,395 criticality benchmarks. However, particular focus has been given to including benchmarks...
Pulsed-neutron die-away (PNDA) experiments can be useful benchmarks to validate neutron thermal scattering laws (TSLs). The experiment uses a neutron generator to impinge a short ($\sim$10$^{-4}$ s), mono-energetic neutron pulse on a target sample. After the pulse, the neutron population within the sample moderates and reaches thermal equilibrium with a fundamental spatial mode and...
The determination of decay heat is a major safety issue for a reactor in operation but also for the transport of burnt fuel and nuclear waste management. The calculation of decay heat through the summation method relies on the combination of reactor simulations to estimate the fuel inventory and on nuclear data: decay properties of the fission products and actinides, fission yields and cross...