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At least 343 records · Page 19
All sourcesNASA NTRSDOE OSTI
DOE OSTI2023

IER 501: Pulsed Neutron Die-Away Experiments at LLNL [Slides]

This presentation notes the purpose of Pulsed Neutron Die Away (PNDA) for Thermal Neutron Scattering Law (TSL) validation. PNDA for TSL validation does not require fissile material. It consists of simple target shapes and compositions and is only sensitive to absorption and scattering of target medium. Well conducted experiments have uncertainties of 0.1% - 0.5%. This presentation also covers Pulsed Neutron Die Away Experiments, while noting previous experiments such as the FY22 PNDA Experiments. The presentation concludes with FY23 benchmarking efforts and a timeline to FY24.

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗
DOE OSTI2018

Comparison of MAVRIC/MONACO and TRIPOLI-4{sup R} simulations of the LLNL pulsed spheres benchmark experiments - 25403

Simulations of the Lawrence Livermore Pulsed Spheres with MAVRIC/Monaco and TRIPOLI-4{sup R} are presented. Both codes use ENDF/B-VII.1 cross section data, but TRIPOLI-4{sup R} also uses cross section data based on JEFF-3.1.1. The MAVRIC/Monaco simulations were performed with the SCALE 6.2.2 release while the TRIPOLI-4{sup R} simulations used an internal development version of the code. For the most part, the simulated and measured neutron counts agree within 30%. Simulated gamma flux data is compared, as well. There are no measured gamma data. The agreement between the simulated gamma flux spectra is often within 10% or less, but there some notable differences, especially when comparing simulations using ENDF/B-VII.1 and JEFF 3.1.1 based cross section data. The comparison of photon simulations suggests that improvements are needed in the cross-section data, cross section processing codes, and/or transport codes and gamma measurement data is needed for experimental validation. (authors)

61 RADIATION PROTECTION AND DOSIMETRY↗
DOE OSTI2018

Testing of ENDF/B-VIII.0 in the GNDS format with LLNL transport codes - 25606

ENDF/B-VIII.0 was released in the Evaluated Nuclear Data Format and the Generalized Nuclear Data Structure format (GNDS), a new international standard for storing nuclear data developed under the auspices of the Nuclear Energy Agency Working Party on Evaluation Cooperation Subgroup 38. GNDS relies on modern coding practices, and offers a structured, flexible and physics-based standard for storing and exchanging nuclear data to address limitations in legacy nuclear data formats such as ENDF-6. GNDS supports the storage of evaluated nuclear data as well as processed data suitable for both deterministic (i.e., multi-group) and Monte Carlo transport codes. Lawrence Livermore National Laboratory has implemented a complete suite of codes to test GNDS data. Simulations for the ENDF/B-VIII.0 cross-section library in GNDS format are presented. Deterministic and Monte Carlo radiation transport simulations with the Ardra and Mercury codes respectively, are validated against reactivities in fast criticality safety benchmark assemblies. Finally, Mercury simulations of {sup 238}U(n,f), {sup 237}Np(n,f) and {sup 239}Pu(n,f) reaction rates in Godiva, Jezebel and Flattop are compared to MCNP results and measured data. (authors)

61 RADIATION PROTECTION AND DOSIMETRY↗