scholarly journals COMPARISON OF TWO FAST REACTOR CROSS SECTION PROCESSING CODES.

1972 ◽  
Author(s):  
R. Kidman
Keyword(s):  
Cross Section ◽  
Fast Reactor ◽  
Reactor Cross Section

scholarly journals FAST REACTOR CROSS-SECTION PROCESSING CODES - IS THERE A DOLLARS WORTH OF DIFFERENCE BETWEEN THEM?

1975 ◽  
pp. 468-490 ◽  
Author(s):  
C.R. Weisbin ◽  
N.M. Greene ◽  
H. Henryson ◽  
R.J. LaBauve ◽  
C. Durston ◽  
...  
Keyword(s):  
Cross Section ◽  
Fast Reactor ◽  
Reactor Cross Section

Development of a Unified Cross-Section Set ADJ2010 Based on Adjustment Technique for Fast Reactor Core Design

2011 ◽  
Vol 59 (2(3)) ◽  
pp. 1357-1360 ◽  
Author(s):  
K. Sugino ◽  
M. Ishikawa ◽  
K. Yokoyama ◽  
Y. Nagaya ◽  
G. Chiba ◽  
...  
Keyword(s):  
Cross Section ◽  
Fast Reactor ◽  
Reactor Core

Generation and validation of a new 121 group coupled (n, γ) cross section library for fast reactor applications

1996 ◽  
Vol 23 (10) ◽  
pp. 791-800 ◽  
Author(s):  
K. Devan ◽  
P. Mohanakrishnan ◽  
V. Gopalakrishnan ◽  
S.M. Lee
Keyword(s):  
Cross Section ◽  
Fast Reactor

The Generation of Few-Group Constants for Fast Reactor Analysis

2016 ◽  
Author(s):  
Xianan Du ◽  
Liangzhi Cao ◽  
Youqi Zheng
Keyword(s):  
Monte Carlo ◽  
Cross Section ◽  
Cross Sections ◽  
Fast Reactor ◽  
Monte Carlo Calculation ◽  
Anisotropic Scattering ◽  
Slowing Down ◽  
Nodal Method ◽  
Reactor Calculation ◽  
Broad Energy

A way to generate the few-group cross sections for fast reactor calculation is presented in this paper. It is based on the three steps computational scheme. In the first step, the ultrafine method is used to solve the slowing down equation based on the ultrafine group cross section generated by NJOY. Optional 0D or 1D calculation is used to collapse energy group into broad energy groups. In the second step, the 2D RZ calculation using SN method is performed to obtain the space dependent neutron spectra to collapse broad energy groups into few groups. The anisotropic scattering is well handled by the direct SN calculation. Finally, the full core calculation is performed by using the 3D SN nodal method. The results are compared with continuous energy Monte-Carlo calculation. Both the cross section generated in the first step and the final keff in the last step are compared. The results match well between the three steps calculation and Monte-Carlo calculation.

Helium Production Cross Section of Boron for Fast-Reactor Neutron Spectra

1975 ◽  
Vol 25 (2) ◽  
pp. 305-329 ◽  
Author(s):  
Harry Farrar ◽  
W. N. McElroy ◽  
E. P. Lippincott
Keyword(s):  
Cross Section ◽  
Fast Reactor ◽  
Production Cross Section ◽  
Production Cross ◽  
Reactor Neutron ◽  
Neutron Spectra ◽  
Fast Reactor Neutron
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