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Technical Brief

U233 Data Evaluation for Criticality Study

[+] Author and Article Information
Mohammad Alrwashdeh

Jordan Research and Training Reactor,
Shafa Badran, P.O Box: 70, Amman, Jordan
e-mail: rawashdeh.80@gmail.com; m.alrwashdeh@jaec.gov.jo

Wang Kan

Department of Engineering Physics, Tsinghua University,
Beijing 100084, China
e-mail: wangkan@mail.tsinghua.edu.cn

Manuscript received June 25, 2015; final manuscript received January 25, 2016; published online June 17, 2016. Assoc. Editor: Michael J. Bluck.

ASME J of Nuclear Rad Sci 2(3), 034501 (Jun 17, 2016) (5 pages) Paper No: NERS-15-1118; doi: 10.1115/1.4032814 History: Received June 25, 2015; Accepted January 25, 2016

The aim of this study is to investigate the available U233 cross section data for adequate calculation of critical benchmark experiments, to calculate the multiplication factor Keff for several benchmarks in both fast and thermal energy ranges. The evaluation of the U233 has been investigated using SAMMY code, in order to generate a useful database for criticality calculations; the computer code FITWR for experimental data fitting shows the same results obtained from the Bayes method included within the SAMMY code, with a slight difference in the results in the evaluated cross sections due to different mathematical methods having different results. Excellent results for the calculated Keff values are obtained for several benchmarks in the thermal and fast benchmarks considered in this study.

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References

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Alrwashdeh, M., Abdalla, A., Yu, J., and Wang, K., “Nuclear Cross Section Statistical Analysis With FITWR Program,” Energy Dev. Front., 2(3), pp. 89–93.
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Leal, L. C., Derrien, H., Harvey, J. A., Guber, K. H., Larson, N. M., and Spencer, R. R., 2001, “R-Matrix Resonance Analysis and Statistical Properties of the Resonance Parameters of U233 in the Neutron Energy Range From Thermal to 600 eV,” Oak Ridge National Laboratory, ORNL/TM-2000/372, Mar. 2001.
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Figures

Grahic Jump Location
Fig. 1

Simple flowchart for FITWR

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