In depletion and transmutation calculation, it is important to solve detailed burnup chains with high computational accuracy and efficiency. This requires the good performance of the burnup algorithms. Nuclide inventory tool (NUIT) is a newly developed nuclide inventory calculation code, which is capable of handling detailed depletion chains by implementing various advanced algorithms. Based on the NUIT code, this paper investigates the accuracy and efficiency of the mini-max polynomial approximation (MMPA) method, and compares it with other burnup solvers in NUIT code. It is concluded that the MMPA method is numerically accurate and efficient for dealing with detailed depletion chains with extremely short half-lived nuclides.

Issue Section:
Research Papers
Keywords:
Nuclear engineering, Reactor physics, Standards, Licensing, Regulatory issues, Codes, Transport theory
Topics:
Algorithms, Chain, Errors, Nuclides, Polynomial approximation, Physics

References

1.
Croff
,
A. G.
,
1980
, “
A User's Manual for the ORIGEN2 Computer Code
,” Union Carbide Corporation for the Department of Energy, Washington, DC, Report No.
ORNL/TM-7175
.http://www.iaea.org/inis/collection/NCLCollectionStore/_Public/11/560/11560149.pdf
2.
Wilson
,
W. B.
,
1993
, “
Accelerator Transmutation Studies at Los Alamos With LAHET, MCNP and CINDER'90
,”
Workshop on Simulation of Accelerator Radiation Environment
, Santa Fe, NM, Jan. 11–15, pp. 3–5.https://inis.iaea.org/search/search.aspx?orig_q=RN:25015509
3.
Leppanen
,
J.
,
2013
, “
Serpent—A Continuous-Energy Monte Carlo Reactor Physics Burnup Calculation Code
,” VTT Technical Research Center of Finland, Espoo, Finland, Report No.
NEA-1840
.http://montecarlo.vtt.fi/download/Serpent_manual.pdf
4.
Cetnar
,
J.
,
2006
, “
General Solution of Bateman Equation for Nuclear Transmutations
,”
Ann. Nucl. Energy
,
33
(
7
), pp. 640–645.
5.
Pusa
,
M.
,
2011
, “
Rational Approximation to the Matrix Exponential in Burnup Calculations
,”
Nucl. Sci. Eng.
,
169
, pp.
155
–
167
.
Google Scholar
Crossref
Search ADS
 
6.
She
,
D.
,
Zhu
,
A.
, and
Wang
,
K.
,
2012
, “
Using Laguerre Polynomials to Compute the Matrix Exponential in Burnup Calculations
,”
International Topical Meeting on Advances in Reactor Physics (PHYSOR 2012)
, Knoxville, TN, Apr. 15–20.
7.
Yosuke
,
K.
,
Go
,
C.
,
Masashi
,
T.
, and
Tadashi
,
N.
,
2015
, “
Numerical Solution of Matrix Exponential in Burn-up Equation Using Mini-Max Polynomial Approximation
,”
Ann. Nucl. Energy
,
80
, pp.
219
–
224
.
Google Scholar
Crossref
Search ADS
 
8.
Brookhaven National Laboratory
,
2009
, “
ENDF/B-VII.0 Library
,” Brookhaven National Laboratory, Upton, NY.
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