Numerical Estimation of Nuclear Decay Heat from Induced Neutron Fission of 235U and 239Pu
Abstract
In this paper, Joint
Evaluated Fission and Fusion (JEFF) Nuclear Data Library has been used to
calculate the nuclear decay heat after a fission burst of 235U and 239Pu for shutdown time up to 105 sec.
This estimation is based on the numerical solution of the linear differential
equations that describe buildups and decays of the fission products. The code
was written in MATLAB, which is fast and easy-access platform. The verification of the current code is carried out by
comparing the numerical results with the measured reported ones. The
discrepancies between the evaluated results and the measured ones show the
reliability of the current calculation.
Keywords
References
- [1] Magill J., Nuclides.net, Springer Berlin Heidelberg(2003).
- [2] Tsoulfanidis N., Nuclear Energy, Springer New York. (2013).
- [3] Bodansky D., Nuclear Energy, Springer New York (2005).
- [4] Nichols A. Nuclear Data Requirements for Decay Heat Calculations, Lectures given at the Workshop on Nuclear Reaction Data and Nuclear Reactors: Physics, Design and Safety, Trieste, 25 Feb. – 28 March, Italy (2002).
- [5] https://rsicc.ornl.gov/codes/ccc/ccc8/ccc-805.html
- [6] S. S. NAFEE, S. A. SHAHEEN, and A. M. AL-RAMADY, “Numerical approach for predicting the decay heat contribution of curium isotopes in the mixed oxide nuclear fuel,” Nuclear Engineering and Design 262, 246, Elsevier BV (2013).
- [7] S. S. NAFEE, A. M. AL-RAMADY, and S. A. SHAHEEN, “Numerical approach to calculate the decay heat of actinides for short cooling time,” Annals of Nuclear Energy 57, 304, Elsevier BV (2013).
- [8] SHERIF. S. NAFEE, AMEER. K. AL-RAMADY, and SALEM. A. SHAHEEN, “Prediction Of The Total Decay Heat From Fast Neutron Fission Of 235U And 239Pu,” Zenodo(2012).
Details
Primary Language
English
Subjects
Metrology, Applied and Industrial Physics
Journal Section
Research Article
Publication Date
October 23, 2020
Submission Date
October 27, 2019
Acceptance Date
July 1, 2020
Published in Issue
Year 2020 Volume: 4 Number: 4