SCALE/DB-Public
This is a collection of public data produced by AMPX or curated from quality sources that the SCALE code system relies on for user problem input.
Brown, Jesse [Oak Ridge National Laboratory (ORNL)↗
Engineering topics
Dunn, Michael
Publications and source records attributed to Dunn, Michael.
2020 Virtual CSEWG Meeting Minutes
The 2020 Annual CSEWG Meeting was an unusual meeting in most respects. It was the most highly attended CSEWG since the 1990s (194 registered attendees with a peak attendance of 170), it was 100% virtual, due to the ongoing COVID-19 pandemic, and it was by all accounts highly successful. In fact, the virtual platform allowed many to participate who otherwise would not have been able to travel for an in-person meeting. We thank the BNL IT team and NNDC staff for making this meeting happen. In these minutes, you will find both a summary of the meeting and lists of action items from this and past CSEWG meetings. Please take a moment and note any actions for which you or others at your institution may be responsible.
73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗
Updated ENDF-6 Format Approval Process [Slides]
The presentation begins by discussing the original ENDF/B-VIII.0 format proposal lifecycle and states that the GNDS Expert Group has developed a gitlab-friendly review process that addresses concerns raised by the format proposal lifecycle. As a result, a revised ENDF/B-VIII.0 format proposal lifecycle has been created. The presentation then discusses the necessary steps in the lifecycle that are as follows: create an issue in the issue tracker, make your changes directly to the manual, submit it for review and final approval. The presentation concludes by discussing two other things, including the transition CI/CD from buildbot system to built-in gitlab CI/CD and that the revised format review process document will follow, pending approval.
73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗
Accurate Development of Thermal Neutron Scattering Cross Section Libraries
The objective of this project is to develop a holistic (fundamental and accurate) approach for generating thermal neutron scattering cross section libraries for a collection of important neutron moderators and reflectors. The primary components of this approach are the physical accuracy and completeness of the generated data libraries. Consequently, for the first time, thermal neutron scattering cross section data libraries will be generated that are based on accurate theoretical models, that are carefully benchmarked against experimental and computational data, and that contain complete covariance information that can be used in propagating the data uncertainties through the various components of the nuclear design and execution process. To achieve this objective, computational and experimental investigations will be performed on a carefully selected subset of materials that play a key role in all stages of the nuclear fuel cycle.
Hawari, Ayman I.↗
Booster propulsion/vehicle impact study
The use of hydrogen RP-1, propane, and methane as fuels for booster engines of launch vehicles is discussed. An automated procedure for integrated launch vehicle, engine sizing, and design optimization was used to define two stage and single stage concepts for minimum dry weight. The two stage vehicles were unmanned and used a flyback booster and partially reusable orbiter. The single stage designs were fully reusable, manned flyback vehicles. Comparisons of these vehicle designs, showing the effects of using different fuels, as well as sensitivity and trending data, are presented. In addition, the automated design technique utilized for the study is described.
Weldon, Vincent↗