Comparison of evaluated nuclear data for neutron irradiation damage calculation in fusion spectra

2021 ◽  
Vol 171 ◽  
pp. 112594
Author(s):  
Shengli Chen ◽  
Yannick Peneliau ◽  
David Bernard
Keyword(s):  
Neutron Irradiation ◽  
Nuclear Data ◽  
Irradiation Damage ◽  
Evaluated Nuclear Data

Effects of Neutron Irradiation on the Mechanical and Electromagnetic Properties of Reactor Pressure Vessel Steels

2017 ◽  
Author(s):  
Li Chengliang ◽  
Shu Guogang ◽  
Chen Jun ◽  
Liu Yi ◽  
Liu Wei ◽  
...  
Keyword(s):  
Neutron Irradiation ◽  
Pressure Vessel ◽  
Power Plants ◽  
Hysteresis Loops ◽  
Reactor Pressure Vessel ◽  
Electromagnetic Properties ◽  
Irradiation Damage ◽  
Indentation Hardness ◽  
Rpv Steel ◽  
Reactor Pressure

The effect of neutron irradiation damage of reactor pressure vessel (RPV) steels is a main failure mode. Accelerated neutron irradiation experiments at 292 °C were conducted on RPV steels, followed by testing of the mechanical, electrical and magnetic properties for both the unirradiated and irradiated steels in a hot laboratory. The results showed that a significant increase in the strength, an obvious decrease in toughness, a corresponding increase in resistivity, and the clockwise turn of the hysteresis loops, resulting in a slight decrease in saturation magnetization when the RPV steel irradiation damage reached 0.0409 dpa; at the same time, the variation rate of the resistivity between the irradiated and unirradiated RPV steels shows good agreement with the variation rates of the mechanical properties parameters, such as nano-indentation hardness, ultimate tensile strength, yield strength at 0.2% offset, upper shelf energy and reference nil ductility transition temperature. Thus, as a complement to destructive mechanical testing, the resistivity variation can be used as a potentially non-destructive evaluation technique for the monitoring of the RPV steel irradiation damage of operational nuclear power plants.

Transfer-induced fission in inverse kinematics: Impact on experimental and evaluated nuclear data bases

2015 ◽  
Vol 51 (12) ◽  
Author(s):  
F. Farget ◽  
M. Caamaño ◽  
D. Ramos ◽  
C. Rodrıguez-Tajes ◽  
K. -H. Schmidt ◽  
...  
Keyword(s):  
Inverse Kinematics ◽  
Nuclear Data ◽  
Data Bases ◽  
Induced Fission ◽  
Evaluated Nuclear Data

scholarly journals CENDL project, the chinese evaluated nuclear data library

2017 ◽  
Vol 146 ◽  
pp. 02002 ◽  
Author(s):  
Zhigang Ge ◽  
Haicheng Wu ◽  
Guochang Chen ◽  
Ruirui Xu
Keyword(s):  
Nuclear Data ◽  
Nuclear Data Library ◽  
Data Library ◽  
Evaluated Nuclear Data

scholarly journals Multi-group cross section library generation for HTGR lattice physics code XPZ

2021 ◽  
Vol 2048 (1) ◽  
pp. 012028
Author(s):  
Lerui Zhang ◽  
Ding She ◽  
Lei Shi ◽  
Richard Chambon ◽  
Alain Hébert
Keyword(s):  
Data Processing ◽  
Cross Section ◽  
Nuclear Data ◽  
Automatic Generation ◽  
Detailed Data ◽  
Processing Scheme ◽  
Processing Module ◽  
Complete Set ◽  
Evaluated Nuclear Data ◽  
High Temperature Gas

Abstract The XPZ code was previously developed for the lattice physics computation in High Temperature Gas-cooled Reactors (HTGRs), which adopted the multi-group cross section library converted from the existing open-source DRAGON library. In this paper, a new format of multi-group cross section library named XPZLIB has been implemented in XPZ code. XPZLIB is designed in binary and HDF5 formats, including detailed data contents for resonance, transport and depletion calculations. A new data-processing module named XPZR is developed based on NJOY-2016 to generate nuclide dependent XPZLIB from the most recent evaluated nuclear data, and besides, the PyNjoy-2016 system is developed for automatic generation of integrated XPZLIB including a complete set of nuclides. The new generated XPZLIB is presented with the XPZ code. Numerical results demonstrate the accuracy of the new library XPZLIB and the reliability of the data processing scheme. Moreover, the influence of different versions of ENDF/B data is investigated.

Sign in / Sign up

Export Citation Format

Share Document