A5018138460- Nuclear reactor physics and engineering
- Nuclear Materials and Properties
- Nuclear Physics and Applications
- Nuclear and radioactivity studies
- Graphite, nuclear technology, radiation studies
- Radioactive contamination and transfer
- Radiation Detection and Scintillator Technologies
- Radioactive element chemistry and processing
- Fusion materials and technologies
- Nuclear Engineering Thermal-Hydraulics
- Thermodynamic and Structural Properties of Metals and Alloys
- Innovative Microfluidic and Catalytic Techniques Innovation
- Particle Detector Development and Performance
- Advanced X-ray and CT Imaging
- Magnetic confinement fusion research
- Nuclear physics research studies
- Electrohydrodynamics and Fluid Dynamics
- Particle accelerators and beam dynamics
- Modular Robots and Swarm Intelligence
- Data Mining Algorithms and Applications
- Engineering Applied Research
- Hydrogen Storage and Materials
- Spacecraft and Cryogenic Technologies
- Statistical Methods in Clinical Trials
- Carcinogens and Genotoxicity Assessment
Los Alamos National Laboratory
2015-2025
Idaho National Laboratory
2021
Oak Ridge National Laboratory
2021
Google (United States)
2018
Lawrence Livermore National Laboratory
2014
Analysis Group (United States)
1999-2004
University of New Mexico
2003
Sandia National Laboratories
1998-2003
Waste Management (United States)
2001
Sandia National Laboratories California
1998
The emergence of microreactor technology has helped to drive supporting nuclear materials qualification and acceptance processes. One essential component in these small reactors is a solid moderator, which typically consists metal hydride cladding. While the behavior performance metal-hydride moderators go back early advanced reactor development for nuclear-powered aviation space propulsion, there remains knowledge gap understanding hydrogen transport–related phenomena irradiation...
As microreactors evolve to become a more affordable and efficient worldwide energy source, the development of moderator material within system decrease required mass low-enriched uranium fuel is important. The use low- instead high-enriched in small nuclear reactors stems from recent national policies associated with nonproliferation. New designs are being developed for range applications space systems particular. Using geometries such as those described this paper, next step advance...
The decay heat rate of five spent nuclear fuel assemblies the pressurized water reactor type were measured by calorimetry at interim storage for in Sweden. Calculations performed 20 organizations using different codes and data libraries resulting 31 results each assembly, spanning most current state-of-the-art practice. calculations based on a selected subset information, such as operating history assembly properties. relative difference between average calculated ranged from 0.6% to 3.3%...
This work provides a summary of selected experimental capabilities being developed to support nonnuclear testing and demonstration technology in microreactors under the U.S. Department Energy's (DOE's) Microreactor Program. Major include Single Primary Heat Extraction Removal Emulator (SPHERE) Agile Non-nuclear Experimental Test Bed (MAGNET). The SPHERE facility allows for controlled steady-state transient heat rejection single pipe using electrical heaters that simulate nuclear heating. is...
Long-term monitoring of spent fuel stored in dry cask storage is currently achieved through the use seals and surveillance. Muon tomography can provide direct imaging that may be useful cases where what known as Continuity Knowledge (CoK) has been lost using former methods. Over past several years, a team from Los Alamos National Laboratory studying muon scattering stopping to examine storage. Data taken on partially loaded Westinghouse MC-10 have demonstrated radiography detect missing...
Following the release of ENDF/B-VII.0 evaluations, an ACE-formatted continuous-energy neutron data library called ENDF70 for MCNP has been produced at Los Alamos National Laboratory. This new contains 387 isotopes and three elements five temperatures: 293.6, 600, 900, 1200, 2500 K. It can be obtained as part MCNP5 1.50 release. The was created using evaluations primarily version 248 NJOY99. A processing script that set up input files NJOY employed checking codes to test content processed...
An integrated nondestructive assay (NDA) system combining active (neutron generator) and passive neutron detection gamma (PG) is being analyzed in order to estimate the amount of plutonium, verify initial enrichment, burnup, cooling time, detect partial defects a spent fuel assembly (SFA). Active signals are measured using differential die-away (DDA), delayed (DN), (DG) techniques. Passive total (TN) counts both gross spectral resolved counts. To quantify how several NDA techniques expected...