Recent Application of Nuclear Data to Fast Reactor Core Analysis and Design in Japan

2005 ◽  
Author(s):  
Makoto Ishikawa
Keyword(s):  
Fast Reactor ◽  
Reactor Core ◽  
Nuclear Data ◽  
Core Analysis ◽  
Recent Application ◽  
Analysis And Design

Neutronic Analyses of the FREYA Experiments in Support of the ALFRED Lead-Cooled Fast Reactor Core Design and Licensing

2019 ◽  
Vol 6 (1) ◽  
Author(s):  
Massimo Sarotto ◽  
Gabriele Firpo ◽  
Anatoly Kochetkov ◽  
Antonin Krása ◽  
Emil Fridman ◽  
...  
Keyword(s):  
Fast Reactor ◽  
Reactor Core ◽  
Nuclear Data ◽  
Control Rod ◽  
The Core ◽  
Major Interest ◽  
Reactor Spectrum ◽  
Data Libraries ◽  
Nuclear Data Libraries ◽  
Sensitivity And Uncertainty Analysis

Abstract During the EURATOM FP7 project FREYA, a number of experiments were performed in a critical core assembled in the VENUS-F zero-power reactor able to reproduce the ALFRED lead-cooled fast reactor spectrum in a dedicated island. The experiments dealt with the measurements of integral and local neutronic parameters, such as the core criticality, the control rod and the lead void reactivity worth, the axial distributions of fission rates for the nuclides of major interest in a fast spectrum, the spectral indices of important actinides (238U, 239Pu, 237 Np) with respect to 235U. With the main aim to validate the neutronic codes adopted for the ALFRED core design, the VENUS-F core and its characterization measurements were simulated with both deterministic (ERANOS) and stochastic (MCNP, SERPENT) codes, by adopting different nuclear data libraries (JEFF, ENDF/B, JENDL, TENDL). This paper summarizes the main results obtained by highlighting a general agreement between measurements and simulations, with few discrepancies for some parameters that are discussed here. Additionally, a sensitivity and uncertainty analysis was performed with deterministic methods for the core reactivity: it clearly indicates that the small over-criticality estimated by the different codes/libraries resulted to be lower than the uncertainties due to nuclear data.

Three-Dimensional Transport Correction in Fast Reactor Core Analysis

1986 ◽  
Vol 23 (10) ◽  
pp. 849-858 ◽  
Author(s):  
Toshihisa YAMAMOTO ◽  
Toshikazu TAKEDA ◽  
Yoshiaki SASAKI ◽  
Yoshiro SAITO
Keyword(s):  
Fast Reactor ◽  
Three Dimensional ◽  
Reactor Core ◽  
Core Analysis

scholarly journals Verification of a two-step code system MCS/RAST-F to fast reactor core analysis

2021 ◽  
Author(s):  
Tuan Quoc Tran ◽  
Alexey Cherezov ◽  
Xianan Du ◽  
Deokjung Lee
Keyword(s):  
Fast Reactor ◽  
Reactor Core ◽  
Core Analysis ◽  
Code System

Influence of nuclear data uncertainties on reactor core calculations

Kerntechnik ◽  
2011 ◽  
Vol 76 (3) ◽  
pp. 174-178 ◽  
Author(s):  
M. Klein ◽  
L. Gallner ◽  
B. Krzykacz-Hausmann ◽  
A. Pautz ◽  
W. Zwermann
Keyword(s):  
Reactor Core ◽  
Nuclear Data

Advances in the analysis of fast reactor core and coolant circuit structures

1992 ◽  
Vol 134 (1) ◽  
pp. 37-58
Author(s):  
Y.W. Chang ◽  
D.T. Eggen ◽  
A. Imazu ◽  
M. Livolant
Keyword(s):  
Fast Reactor ◽  
Reactor Core ◽  
Coolant Circuit
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