Nuclear Data and Resonance Self-Shielding Method
A special issue of Journal of Nuclear Engineering (ISSN 2673-4362).
Deadline for manuscript submissions: closed (31 January 2024) | Viewed by 528
Special Issue Editor
Interests: computational reactor physics; nuclear data; transport and diffusion theory; resonance self-shielding methods; modeling and simulation; in-core fuel management; multiphysics simulation
Special Issues, Collections and Topics in MDPI journals
Special Issue Information
Dear Colleagues,
Multi-group deterministic transport calculations are performed to prepare homogenized few-group cross-sections for three-dimensional reactor core neutronic analysis using nodal diffusion or low-order transport calculations. The accuracy of the multi-group transport results is dependent upon the cross-section processing and resonance self-shielding methods. As computing capacity significantly increases, continuous energy Monte Carlo calculations can be used to replace the role of the multi-group deterministic transport to generate few-group cross-sections for nodal diffusion calculation. However, Monte Carlo calculation is still very expensive in computing time and includes limitations in computing capacity for whole core simulations. Recently, direct multi-group deterministic transport may be a substitute to the nodal diffusion for whole reactor core analysis, and has recently been successful, as demonstrated by DeCART, GENESIS, nTRACER, PROTEUS, Rattlesnake, VERA-MPACT, etc. One of the technical challenges in this approach concerns how to efficiently and precisely process multi-group cross-sections through resonance self-shielding calculation for multi-physics and large-scale problems.
Various resonance self-shielding methods have been developed for various transport lattice codes such as AEGIS, APOLLO, CASMO, DRAGON, GALAXY, HELIOS, KARMA, LANCER, MC2-3, PARAGON, SCALE-XSProc and Polaris, STREAM, WIMS, etc. In addition, new resonance self-shielding methods are under development and proposed for better performance. This Special Issue of JNE will focus on state-of-the-art nuclear data processing and resonance self-shielding methods developed and investigated for various deterministic transport codes. The relevant topics include an assessment of various evaluated nuclear data such as ENDF/B, JEFF, and JENDL, using multi-group deterministic calculations, nuclear data processing and resonance self-shielding methods in the state-of-the-art transport codes, and newly proposed resonance self-shielding methods for multi-physics large-scale simulation.
Dr. Kang Seog Kim
Guest Editor
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Keywords
- multi-group deterministic transport
- nuclear data processing
- assessment of evaluated nuclear data
- resonance self-shielding
- reactor physics
- multi-physics large-scale simulation
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