integral experiment
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Author(s):  
Shoji Nakamura ◽  
Yosuke Toh ◽  
Atsushi Kimura ◽  
Yuichi Hatsukawa ◽  
Hideo Harada

2021 ◽  
Vol 47 (3) ◽  
pp. 150-162
Author(s):  
G. Yu. Mozgunov ◽  
P. Yu. Minaev ◽  
A. S. Pozanenko

2020 ◽  
Vol 194 (10) ◽  
pp. 894-902
Author(s):  
Nnaemeka Nnamani ◽  
Karl Van Bibber ◽  
Lee A. Bernstein ◽  
Jasmina L. Vujic ◽  
Jonathan T. Morrell ◽  
...  

2020 ◽  
Author(s):  
D. Hayes ◽  
G. McKenzie ◽  
J. Hutchinson ◽  
J. Goda ◽  
R. Sanchez ◽  
...  
Keyword(s):  

2020 ◽  
Vol 239 ◽  
pp. 01032
Author(s):  
Shengli Chen ◽  
Gilles Noguere ◽  
David Bernard ◽  
Cyrille De Saint Jean ◽  
Jean Tommasi

Neutron-induced cross section is one of the key quantities in nuclear physics and nuclear engineering. The integral experiment can give good feedback to the cross sections with low uncertainties. Using the optical model and statistical model, the neutron-induced total and capture cross sections of153Eu are revaluated according to the experimental microscopic total cross sections and the PROFIL-2 integral experiment. The corresponding uncertainties and covariances are determined with the data assimilation method implemented in CONRAD code. On the other hand, the previous interpretation of the PROFIL-2 experiment showed that JEFF-3.1 overestimates the neutron-induced capture cross section of 151 Eu by a factor of 2. Further analysis performed in the present work points out that the large difference between calculation and experimental data is mainly due to the lack of152m1 Eu in ERANOS code, which was used to interpret the PROFIL-2 experiment. The correction of 152m1Eu on the interpretation largely reduces the difference between JEFF-3.1 and PROFIL-2 and shows the agreement between the PROFIL-2 integral experiment and other microscopic measurements. The revaluated neutron-induced total and capture cross sections of 151 Eu and 153Eu correspond well with both the microscopic experimental measurements and the PROFIL-2 integral experiment.


2019 ◽  
Author(s):  
Gary A. Harms ◽  
Michael L. Zerkle ◽  
Justin B. Clarity ◽  
David P. Heinrichs

2019 ◽  
Vol 211 ◽  
pp. 07001 ◽  
Author(s):  
D. Kumar ◽  
S. B. Alam ◽  
H. Sjöstrand ◽  
J. M. Palau ◽  
C. De Saint Jean

Nuclear data used in designing of various nuclear applications (e.g., core design of reactors) is improved by using integral experiments. To utilize the past critical experimental data to the reactor design work, a typical procedure for the nuclear data adjustment is based on the Bayesian theory (least-square technique or Monte-Carlo). In this method, the nuclear data parameters are optimized by the inclusion of the experimental information using a Bayesian inference. The selection of integral experiments is based on the availability of well-documented specifications and experimental data. Data points with large uncertainties or large residuals (outliers) may affect the accuracy of the adjustment. Hence, in the adjustment process, it is very important to study the influence of experiments as well as of the prior nuclear data on the adjusted results. In this work, the influence of each individual reaction (related to nuclear data) is analyzed using the concept of Cook’s distance. First, JEZEBEL (Pu239, Pu240 and Pu241) integral experiment is considered for data assimilation and then the transposition of results on ASTRID fast reactor concept is discussed.


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