A5023768891- Nuclear reactor physics and engineering
- Nuclear Physics and Applications
- Nuclear Materials and Properties
- Radiation Detection and Scintillator Technologies
- Graphite, nuclear technology, radiation studies
- Nuclear and radioactivity studies
- Radioactive contamination and transfer
- Radiation Therapy and Dosimetry
- Nuclear physics research studies
- Probabilistic and Robust Engineering Design
- Particle Detector Development and Performance
- Particle Accelerators and Free-Electron Lasers
- Radioactive element chemistry and processing
- Scientific Measurement and Uncertainty Evaluation
- Higher Education Learning Practices
- Structural Health Monitoring Techniques
- Electron and X-Ray Spectroscopy Techniques
- Particle physics theoretical and experimental studies
United States Naval Research Laboratory
2019-2024
National Nuclear Laboratory
2024
University of Wisconsin System
2017
Bechtel (United States)
2014
Rensselaer Polytechnic Institute
2003-2006
Lockheed Martin (United States)
2006
AbstractThis paper considers the problem of accurately representing temperature dependence neutron cross-section data in transport problems when there are many nuclides and distributions vary significantly with both space time. An approach involving interpolation between nuclear libraries at various reference temperatures is investigated. Reference obtained by Doppler broadening cross sections to desired using NJOY code system. Several schemes over intervals studied. Interpolated values...
MC21 is a continuous-energy Monte Carlo radiation transport code for the calculation of steady-state spatial distributions reaction rates in three-dimensional models. The supports neutron and photon fixed source problems, as well iterated-fission-source (eigenvalue) problems. has been designed optimized to support large-scale problems reactor physics, shielding, criticality analysis applications. also many in-line feedback effects, including depletion, thermal feedback, xenon eigenvalue...
In order to test the performance of new neutron thermal scattering law (TSL) evaluations it is desirable have experimental data that highly sensitive TSL and provides high fidelity information on energy dependent evaluations. Three relevant experiments are discussed including: accurate total cross section measurements, die-away experiments, leakage experiments. The setups results reviewed examples provided for some moderators including polyethylene, Plexiglas, YHx. For preformed thus far,...
Recently, a cold moderator was designed and developed for use at the Rensselaer Polytechnic Institute Linear Accelerator (RPI LINAC). This proved to easily safely couple an existing neutron producing target, while enhancing flux below 0.02 eV by up factor of 8 cooling polyethylene down 29 K. capability allowed significantly improved counting statistics not previously possible due poor signal background ratio. Additionally, testing performed characterize energy resolution new system found...
The nuclear data group at the RPI Gaerttner LINAC Laboratory uses a 60 MeV pulsed electron to produce short pulses of neutrons and perform cross section other measurements in wide energy range from below 1 meV about 20 MeV. This paper will cover several recent activities that are interest applications. Interest thermal neutron scattering evaluations prompted need for accurate total validation. To improve flux sub-thermal region (below 0.01 eV) cold moderator was designed installed. A...
Measurements of delayed fission product gamma-ray transmission through low-enriched UO2 fuel pin lattices in an air medium were conducted at the Rensselaer Polytechnic Institute Reactor Critical Facility (RCF). The RCF core consists excess Special Power Excursion Test pins enriched to 4.81 wt% 235U and clad stainless steel. An experimental apparatus was constructed hold various arrangements lattices. consisted a single activated source taken from reactor surrounded by inactive medium. A...
The electron linear accelerator housed in the Gaerttner Linear Accelerator Center at Rensselaer Polytechnic Institute was used to generate a pulsed neutron source measure total cross section of tantalum, titanium, and zirconium from 0.4 25 MeV. Neutron transmission measurements were made using time-of-flight method with flight paths approximately 100 250 m. long combined narrow pulse widths, fast detector responses, electronics, data collection system provide good energy resolution for...
Ionization chambers were designed and constructed to determine the kerma rates in various materials within several centimeters of a Training, Research, Isotopes, General Atomics (TRIGA) reactor core operating at 1 MW. The primary aim this article was compare measurements with advanced Monte Carlo code calculations nuclear heating. Wall thickness, collection gap, fill gas pressure chosen satisfy Bragg-Gray criteria, so that measured ionization current related rate wall material. Chamber...
Yttrium hydride serves as a neutron moderator material that enables compact, high temperature nuclear reactors. However, in order to accurately design and simulate system relying upon yttrium hydride, the fundamental data of must be well understood. Thermal scattering law (TSL) evaluations represent an important aspect thermal can drastically alter multiplication factor system. Therefore, support evaluation validation for researchers at Rensselaer Polytechnic Institute (RPI) performed total...