4. 輸送計算コードと断面積ライブラリー(<講座> 中性子工学III)

概要

論文の詳細を見る
In fusion neutronics, one needs to perform transport calculations to predict neutron and photon fluxes and a number of important nuclear responses. To treat the special features of fusion neutronics, the calculation methods developed for the fission reactors have been modified, and the prediction accuracy has been much improved. In this chapter, the transport codes and their solution methods widely used in Japan are presented together with cross section libraries for those codes.
社団法人プラズマ・核融合学会の論文
1995-12-25