This study investigates the reactor core physical properties of the AP1000®, which applies the MCNP4a program to model the AP1000 reactor core with the parameters and data from the design control document (DCD, Rev. 19) of the AP1000 Nuclear Power Plant, which has been submitted to the nuclear regulatory commission (NRC). The model is applied to calculate and verify the physical parameters of AP1000 core design. The results match well with the design values in the DCD of the AP1000 nuclear power plant. The model will be modified according to the actual reactor core arrangement, such as AP1000 reactors at China's Sanmen and Haiyang sites, and then compared with the commissioning test results in the future.

References

References
1.
NRC
,
2011
, “
Westinghouse AP1000 Design Control Document Rev. 19
,” U.S. Nuclear Regulatory Commission, Washington, DC, accessed June 21, 2011, http://www.nrc.gov/docs/ML1117/ML11171A500.html
2.
Briesmeister
,
J. F.
,
1993
, “
MCNP-A General Monte Carlo N-Particle Transport Code, Version 4A
,” Los Alamos National Laboratory, Los Alamos, NM, Technical Report No. LA-12625.
3.
Godfrey
,
A. T.
,
2014
, “
VERA Core Physics Benchmark Progression Problem Specifications
,” Oak Ridge National Laboratory, Oak Ridge, TN, Report No.
CASL-U-2012-0131-004
.https://www.casl.gov/sites/default/files/docs/CASL-U-2012-0131-004.pdf
4.
Franceschini
,
F.
,
Godfrey
,
A.
,
Kulesza
,
J.
, and
Oelrich
,
R.
,
2014
, “
Zero Power Physics Test Simulations for the AP1000® PWR
,” Westinghouse, Pittsburgh, PA, Report No. CASL-U-2014-0012-001.
5.
Freudenreich
,
W. E.
,
Gruppelaar
,
H.
,
Hogenbirk
,
A.
, and
Koning
,
A. J.
,
1998
, “
Accelerator Driven Systems TH-ADS Benchmark Calculations
,” ECN-Nuclear Research Section, Nuclear & Reactor Physics, Petten, The Netherlands, Report No.
ECN-R-97-012
.https://www.researchgate.net/publication/299347947_Accelerator-driven-systems_TH-ADS_benchmark_calculations_Results_of_stage_1
6.
Mohapatra
,
D. K.
,
Sunny
,
C. S.
,
Mohanakrishnan
,
P.
, and
Subbaiah
,
K. V.
,
2004
, “
Monte Carlo Modeling of KAMINI
,”
Ann. Nucl. Energy
,
31
(
18
), pp.
2185
2194
.
7.
Roger
,
B.
,
2009
, “
Criticality Calculations With MCNP5: A Primer
,”
Los Alamos National Laboratory
,
Los Alamos, NM
, Report No. LA-UR-09-00380.
8.
Branislav
,
V.
,
Jakub
,
L.
,
Gabriel
,
F.
,
Jan
,
H.
,
Róbert
,
H.
,
Martin
,
P.
,
Vladimír
,
S.
, and
Juraj
,
Š.
,
2014
, “
Temperature Coefficients Calculation for the First Fuel Loading of NPP Mochovce 3–4
,”
Ann. Nucl. Energy
,
63
, pp.
646
652
.
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