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 432

Special Issue Editor


E-Mail Website
Guest Editor
Oak Ridge National Laboratory, 1 Bethel Valley Road, Oak Ridge, TN 37830, USA
Interests: computational reactor physics; nuclear data; transport and diffusion theory; resonance self-shielding methods; modeling and simulation; in-core fuel management; multiphysics simulation

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

Published Papers

There is no accepted submissions to this special issue at this moment.
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