Abstract

The main purpose of this work is to study the possibility of using the few-group approximation for calculation of some neutron-physical characteristics of VVER-1000 core by means of special version of Monte Carlo Universal code. The Monte Carlo method for VVER-1000 core neutron-physical characteristics calculation using the few-group approximation with an estimate of neutron cross sections “by location” was provided and tested in this research. The reduction of calculation time due to the transition from a pointwise model of representation of cross sections to the few-group approximation and methodical error of this approach were evaluated. Optimal number of energy groups was determined. It was found that consideration of the scattering anisotropy leads to a significant decrease in methodical error. Ways of further reduction of methodical error were worked out.

Issue Section:
Technical Briefs
Topics:
Approximation, Cross section (Physics), Electromagnetic scattering, Errors, Neutrons, Radiation scattering, Scattering (Physics), Fuels, Anisotropy

References

1.
Kotlyar
,
D.
,
Shaposhnik
,
Y.
,
Fridman
,
E.
, and
Shwageraus
,
E.
,
2011
, “
Coupled Neutronic Thermo-Hydraulic Analysis of Full PWR Core With Monte Carlo Based BGCore System
,”
Nucl. Eng. Des.
,
241
(
9
), pp.
3777
–
3786
.10.1016/j.nucengdes.2011.07.028
Google Scholar
Crossref
Search ADS
 
2.
Griesheimer
,
D.
,
Gill
,
D.
, and
Nease
,
B. EA.
,
2013
, “
MC21 v.6.0—A Continuous-Energy Monte Carlo Particle Transport Code With Integrated Reactor Feedback Capabilities
,”
Joint International Conference on Supercomputing in Nuclear Applications and Monte Carlo 2013
, Paris, France, 27–31 Oct., pp.
65
–
79
.https://www.cs.unc.edu/~dave/mySite/media/papers/2013-MC21v6-SNAMC.pdf
Google Scholar
Crossref
Search ADS
 
3.
Bikeev
,
A. S.
,
Bogdanova
,
E. V.
,
Kosourov
,
E. K.
,
Shkarovsky
,
D. A.
, and
Kalugin
,
M. A.
,
2018
, “
Study of Neutron-Physical Characteristics of VVER-1200 Considering Feedbacks Using MCU Monte Carlo Code
,”
Kerntechnik
,
83
(
4
), pp.
299
–
8
.10.3139/124.110863
Google Scholar
Crossref
Search ADS
 
4.
Kalugin
,
M. A.
,
Oleynik
,
D. S.
, and
Shkarovsky
,
D. A.
,
2015
, “
Overview of the MCU Monte Carlo Software Package
,”
Ann. Nucl. Energy
,
82
, pp.
54
–
62
.10.1016/j.anucene.2014.08.032
Google Scholar
Crossref
Search ADS
 
5.
Akkurt
,
H.
, and
Abdurrahman
,
N. M.
,
1998
, “
Neutronic Benchmarks for the Utilization of Mixed-Oxide Fuel
,” Joint U.S. Russian Progress Report for Fiscal Year 1997, ORNL, Oak Ridge, TN.
6.
Organisation for Economic Co-Operation and Development—Nuclear Energy Agency
,
2002
,
A VVER-1000 Leu and MOX Assembly Computational Benchmark Specification and Results
,
Nuclear Energy Agency of the OECD (NEA)
: Organisation for Economic Co-Operation and Development—Nuclear Energy Agency,
Paris, France
.
7.
Bikeev
,
A. S.
,
Kalugin
,
M.
,
Shkarovsky
,
D. A.
, and
Shcherenko
,
A. I.
,
2018
, “
Simulation of VVER 1000 Startup Physics Tests Using the MCU Monte Carlo Code
,”
Ann. Nucl. Energy
,
117
, pp.
60
–
66
.10.1016/j.anucene.2018.03.001
Google Scholar
Crossref
Search ADS
 
8.
Nikolaev
,
M. N.
,
Ryazanov
,
B. G.
, and
Savoskin
,
M. M.
,
1984
,
Multi-Group Approach in Neutron Transport Theory
,
Eneroatomizdat Publishing
,
Moscow, Russia
.
9.
Frank-Kamenetskii
,
A. D.
,
1978
,
Modelirovanie Traektorij Nejtronov Pri Raschyote Reaktorov Metodom Monte-Karlo
,
Atomisdat Publishing
,
Moscow, Russia
.
10.
The Federal Collective Usage Center
,
2019
, “
Complex for Simulation and Data Processing for Mega-Science Facilities” at NRC “Kurchatov Institute
,” Moscow, Russia, accessed Aug. 25, 2021, http://ckp.nrcki.ru/
11.
Bolobov
,
P. A.
,
Lazarenko
,
A. P.
, and
Tomilov
,
M. J.
,
2008
, “
Development of the Code Package KASKAD for Calculations of WWERs
,”
Proceedings of the Eighteenth Symposium of Atomic Energy Research
,
Kiadja and KFKI Atomenergia Kutatointezet
, Eger,
Hungary
, Oct. 6–10. https://www.osti.gov/etdeweb/servlets/purl/21186063
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