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"Humanities and Science University Journal" №15 (Physical and mathematical, biological and technical science), 2015

Development of the Inherent Thrermohydraulic Code in the Course of SimInTech Environment Capabilities Development

N. G. Chernetsov, Yu. V. Chernobrovkin, V. V. Khodakovsky, K. A. Timofeev, S. V. Orekhov
Price: 50 руб.
 Thermohydraulic code intended for the calculation of dynamics of compressible and non-compressible coolant main parameters behavior in the thermohydraulic circuits of a random topology is developed as a part of the domestic SimInTech environment
for modeling complicated logical-dynamical systems. The article describes the main approaches to the conservation equations solution implemented in the code. The authors provide the example for the thermohydraulic code application to model an advanced lead-cooled reactor plant BR-1200.
Keywords: thermohydraulic code, conservation equations, backward differentiation
formula, compressibility, numerical modeling
REFERENCES
1. The U.S. Nuclear Regulatory Commission (NRC) about computer codes.
Retrieved November 1, 2015, from http://www.nrc.gov/about-nrc/regulatory/research/
safetycodes.html
2. RELAP5-3D Code Manual, Vol. I: Code Structure, System Models, and Solution
Methods. INEEL EXT-98-00834, Rev. 2.4, 2005. Retrieved November 1, 2015, from
http://www4vip.inl.gov/relap5/r5manuals/ver_2_4/vol1_v2_4.pdf
3. Belzepkin, V.V., Kukhtevich, V.O., Obraztsov, E.P., Migrov, Yu.A., Shaleninov, A.A., & Deulin, A.A. (2013, May). Hardware-Software Complex “Virtual NPP
Unit with VVER” (HSC “VPU”) for Testing Design Solutions of NPP-2006. The 8th
International Scientific and Research Conference “Provision of Safety for NPP with
VVER”, OKB “Gidropress”, Podolsk, Russia.
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Software. Humanities and science university journal, 2013, 5, 144–156.
5. Bolnov, V.A., Zotov, I.S., Malkin, S.A., & Ushatikov, A.S. Experience of Creation
of Modeling Complex for NPP with RP BN-1200 [Опыт создания моделирующего
комплекса для АЭС с РУ БН-1200]. Atomic Project, 2014, 2014, 19, 62–63.
6. Yudov, Yu.V. Development of Double-Fluid Model of Circuit Thermohydraulics
of Water-Cooled Reactor Units [Разработка двухжидкостной модели контурной
теплогидравлики реакторных установок с водяным теплоносителем] (PhD Thesis,
Sosnovy Bor, Russia). 2001.
7. Russian Federation, Patent for invention № 2545098 "Lead-Cooled Fast Neutron
Reactor Plant", priority of invention 31 January 2014.
Price: 50 рублей
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