scholarly journals THE SOURCE JERK INTEGRALMETHOD FOR SUB-CRITICALITY MEASUREMENTS IN ADS

2021 ◽  
Vol 247 ◽  
pp. 08002
Author(s):  
A. Kochetkov ◽  
A. Billebaud ◽  
S. Chabod ◽  
A. Krása ◽  
F.-R. Lecolley ◽  
...  
Keyword(s):  
Dead Time ◽  
Power Reactor ◽  
Nuclear Data ◽  
Start Up ◽  
Nuclear Data Library ◽  
And Control ◽  
Control Rods ◽  
Fission Chambers ◽  
Data Library ◽  
Evaluated Nuclear Data

Three sub-critical (SC) core configurations were investigated in the VENUS-F zero power reactor coupled with the GENEPI-3C accelerator. The SC10 and SC12 were a mock-up of a MYRRHA start-up core and SC11 represented a more complex MYRRHA core loaded with various types of in-pile-sections. The sub-criticality of 11 variants of these VENUS-F cores was changed in several steps from -6$ down to -30$ using the safety and control rods. Their sub-criticalities were determined with the Source Jerk Integral (SJI) method using 11 fission chambers located all over the reactor. For the data analysis, the 8-group delayed neutron parameters from the JEFF-3.1.2 evaluated nuclear data library were used. Reliability and reproducibility of the experimental results were tested by repeating the measurements, swapping the detectors and varying the accelerator beam intensity, thus changing the detector count rates and verifying the validity of the dead time corrections. The obtained results are compared with MCNP calculations.

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

The Updated Vversion of Chinese Evaluated Nuclear Data Library (CENDL-3.1)

2011 ◽  
Vol 59 (2(3)) ◽  
pp. 1052-1056 ◽  
Author(s):  
Z. G. Ge ◽  
Z. X. Zhao ◽  
H. H. Xia ◽  
Y. X. Zhuang ◽  
T. J. Liu ◽  
...  
Keyword(s):  
Nuclear Data ◽  
Nuclear Data Library ◽  
Data Library ◽  
Evaluated Nuclear Data

scholarly journals Improved Mixed Oxide Fuel Calculations with the Evaluated Nuclear Data Library JEFF-3.2

2016 ◽  
Vol 182 (2) ◽  
pp. 135-150
Author(s):  
G. Noguere ◽  
D. Bernard ◽  
P. Blaise ◽  
O. Bouland ◽  
L. Leal ◽  
...  
Keyword(s):  
Mixed Oxide ◽  
Nuclear Data ◽  
Oxide Fuel ◽  
Mixed Oxide Fuel ◽  
Nuclear Data Library ◽  
Data Library ◽  
Evaluated Nuclear Data

scholarly journals ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology

2006 ◽  
Vol 107 (12) ◽  
pp. 2931-3060 ◽  
Author(s):  
M.B. Chadwick ◽  
P. Obložinský ◽  
M. Herman ◽  
N.M. Greene ◽  
R.D. McKnight ◽  
...  
Keyword(s):  
Science And Technology ◽  
Nuclear Data ◽  
Next Generation ◽  
Nuclear Science ◽  
Nuclear Data Library ◽  
Data Library ◽  
Evaluated Nuclear Data

scholarly journals CENDL-3.2: The new version of Chinese general purpose evaluated nuclear data library

2020 ◽  
Vol 239 ◽  
pp. 09001
Author(s):  
Zhigang Ge ◽  
Ruirui Xu ◽  
Haicheng Wu ◽  
Yue Zhang ◽  
Guochang Chen ◽  
...  
Keyword(s):  
Cross Sections ◽  
Nuclear Data ◽  
General Purpose ◽  
Reaction Cross ◽  
Main Reaction ◽  
Science And Engineering ◽  
Nuclear Data Library ◽  
Evaluation Techniques ◽  
Data Library ◽  
Evaluated Nuclear Data

A new version of Chinese Evaluated Nuclear Data Library, namely CENDL-3.2, has been completed under the joint efforts of CENDL working group. This library is constructed with the general purpose to provide high-quality nuclear data for the modern nuclear science and engineering. 272 nuclides from light to heavy are covered in CENDL-3.2 in total and the data for 134 nuclides are new or updated evaluations in energy region of 10-5 eV-20 MeV. The data of most of the key nuclides in nuclear application like U, Pu, Th, Fe et al. have been revised and improved, and various evaluation techniques have been developed to produce the nuclear data with good quality. Moreover, model dependent covariances data for main reaction cross sections are added for 70 fission product nuclides. To assess the accuracy of CENDL-3.2 in application, the data have been tested with the criticality and shielding benchmarks collected in ENDITS-1.0.

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