Artemov V.G., Artemova L.M., Korotaev V.G., Kuznetsov A.N.
Alexandrov Research Institute of Technoloqy, Sosnovy Bor, Russia
The paper presents the SAPFIR_95&RC_VVER modeling results for the test task based on full-scale experiment performed at VVER-1000 reactor plant. In this experiment, a transient mode was implemented with the disconnection of two adjacent out of four operating main circulation pumps (MCP) and control rods insertion to compensate the reactivity. The test task was applied to develop methods of non-stationary calculation of pinwise power density using the programs for computations of neutronic and thermal-hydraulic characteristics of VVER type reactors. The SAPFIR_95&RC_VVER program package has two methods for calculating the pinwise power density: superposition method of micro- and macro-flux, and the fine-grid method, in which the nodes of the radial calculation grid in the core coincide with the centers of fuel rods in the fuel assembly. Both approaches are implemented to solve steady-state and transient problems. Transient simulations are performed by coupling the SAPFIR_95&RC_VVER and the KORSAR thermal-hydraulic code.
The paper describes the neutronic models of the VVER-1000 reactor core and solving this test problem by the superposition and fine-grid methods. The results for changes in the pinwise power density under dynamic regime calculated by both methods are presented.
1. Konyukhova A.I. Razvitie methodov razchetnogo obosnovania bezopasnosti RU VVER s primineniem potvelnogo modelirovania aktivnoy zony. Diss. kand. tehn. nauk [Development of computational methods for justification of the VVER reactor safety using the portfolio modeling of the core. Cand. tech. sci. diss.]. Moscow, 2020.
2. Gordienko P.V. Modelirovanie nestacionarnih neitronno-fizicheskih processov v reaktorah VVER s potvelnoi detalizaciei. Diss. kand. tehn. nauk [Modeling of nonstationary neutronic processes in VVER reactors with pinwise details. Cand. tech. sci. diss.]. Moscow, 2014.
3. Artemov V.G., Artemova L.M., Korotaev V.G., Mikheev P.A., Shemaev Yu.P. Analys temperaturnogo sostoyaniya tvelov na osnove sopryagennogo neytronno-fzicheskogo i teplogidravlicheskogo rascheta [Analysis of fuel element thermal states based on the coupled neutronic and thermal hydraulic calculations]. Voprosy atomnoy nauki i tekhniki. Seriya: Yaderno-reaktornyye konstanty – Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2014, no. 4, pp. 24–29.
4. Artemov V.G., Artemova L.M., Elshin A.V., Ivanov A.S., Karpov A.S., Piskarev A.V., Sergeev V.K., Shemaev Yu.P. Sozdanie kompleksa program dla rascheta neitronno-fizicheskih harakteristik reaktorov tipa VVER[Creation of program package for calculating the neutronic characteristics of VVER type reactors]. Sb. nauchnykh trudov NITI im. Aleksandrova “Tekhnologiya i sistemy obespecheniya zhiznennogo tsikla yadernykh ustanovok” [Proc. of Alexandrov NITI “Nuclear propulsion reactor plants. Life cycle management technologies”. Issue 5]. Sankt-Peterburg, Mendeleev Publ., 2007. Pp. 20–34. Available at: https://sapfir.niti.ru/?page_id=65 (accessed 16.08.2023).
5. SAPFIR_95.1. Attestacionniy passport programmnogo sredstva No. 390 ot 16.12.2015. Federalnaya slugba po ekologcheskomu, tehnologicheskomu i atomnomy nadzory [Certification passport No. 390 of 16.12.2015 issued by Federal Service for Ecological, Technological and Nuclear Supervision].
6. Artemov V.G., Ivanov A.S., Kuznetsov A.N., Shemaev Yu.P. Kombinirovanniy method rascheta potvelnogo energovidelenia v komplekse program Sapfir_95&RC_VVER[The combined method for pin-to-pin power density calculation with the SAPFIR_95&RC_VVER program package]. Voprosy atomnoy nauki i tekhniki. Seriya: Yaderno-reaktornyye konstanty – Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2014, no. 3, pp. 85–89.
7. Sapfir_95&RC_VVER.2. Certification passport No. 321 of 18.04.2013 issued by Federal Service for Ecological, Technological and Nuclear Supervision.
8. Sapfir_95&RC_micro. Certification passport No. 496 of 19.12.2019 issued by Federal Service for Ecological, Technological and Nuclear Supervision.
9. KORSAR/GP. Certification passport No. 263 of 23.09.2009 issued by Federal Service for Ecological, Technological and Nuclear Supervision.
10. Alekhin G.V., Belyaev Yu.V., Zaitsev S.I., Bykov M.A., Nadinsky Yu.N., Kudryavtsev O.V. Razrabotka obyedinennogo kompleksa DKM dlya rascheta lokalnih parametrov v aktivnoi zone VVER s uchetom trehmernoy kinetiki[Development of a combined DKM program package for calculating local parameters in the VVER core taking into account three-dimensional kinetics]. Trudi konferencii 3-i nauchno-tehnicheskoy konferencii “Obespechenie besopasnosti AES s VVER” [Proc. of the 3d Scientific and Technical Conference “Ensuring the safety on NPPs with VVER reactors”]. Podolsk, 26–30 of May 2003. vol. 2, pp. 25–49.
11. Artemov V.G., Kuznetsov A.N. Verifikaciya potvelnoy modeli SAPFIR_95&RC_VVER pri modelirovanii vygoraniya zagruzok energoblokov[Pin-to-pin model verification of the SAPFIR_95&RC_VVER program package during the burn-up simulation of VVER loadings]. Voprosy atomnoy nauki i tekhniki. Seriya: Yaderno-reaktornyye konstanty – Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2018, no. 1, pp. 35–46.
12. Artemov V.G., Kuznetsov A.N., Kurakin K.Yu., Tihomirov A.V. Ocenka vliyaniya plotnosti teplonositelya na tochnost' rascheta potvelnogo energovydeleniya[Impact assessment of coolant density variation on the accuracy of VVER energy release calculation]. Voprosy atomnoy nauki i tekhniki. Seriya: Yaderno-reaktornyye konstanty – Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2019, no. 3, pp. 115–122.
13. Avramova M., Denisenko A., Denisova M., Gordienko P., Ivanov K., Nikonov S., Pasichnyk I., Shumskiy B., Sizov R., Velkov K. EGMPEPV Benchmark “Rostov-2”. Proc. of the 27th Symposium of AER on VVER Reactor Physics and Reactor Safety. Germany, Munich, 17–20 October, 2017.
14. Artemov V.G., Artemova L.M., Korotaev V.G., Kuznetsov A.N. Rezultaty modelirovaniya testovoy zadachi “Benchmark Rostov 2” s ispolzovaniem kompleksa programm SAPFIR_95&RC_VVER i KORSAR [Results of “Benchmark Rostov 2” test task simulation using SAPFIR_95&RC_VVER and KORSAR program package]. Voprosy atomnoy nauki i tekhniki. Seriya: Yaderno-reaktornyye konstanty – Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2019, no. 4, pp. 118–127.
