A 2D/1D Algorithm for Effective Cross-Section Generation in Fast Reactor Neutronic Transport Calculations
Author:
Affiliation:
1. CEA, DEN, DER, SPRC, Cadarache, Saint-Paul-lez-Durance F-13108, France
Funder
Commissariat à l’Énergie Atomique et aux Énergies Alternatives
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering
Link
https://www.tandfonline.com/doi/pdf/10.1080/00295639.2018.1480190
Reference18 articles.
1. PROSPECTS IN DETERMINISTIC THREE-DIMENSIONAL WHOLE-CORE TRANSPORT CALCULATIONS
2. Neutronic calculation of an axially heterogeneous ASTRID fuel assembly with APOLLO3®: Analysis of biases and foreseen improvements
3. Accelerated polynomial axial expansions for full 3D neutron transport MOC in the APOLLO3® code system as applied to the ASTRID fast breeder reactor
4. Assembly homogenization techniques for core calculations
5. Development of a Third-Generation Superhomogénéisation Method for the Homogenization of a Pressurized Water Reactor Assembly
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