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Published: 2016-03-30
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DOI: https://doi.org/10.53747/jnst.v6i1.139
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Vol. 6 No. 1 (2016)
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Articles
How to Cite
Peng Hong, L., Surian, P., Tagor Malem, S., & Tran Hoai, N. (2016). Status on development and verification of reactivity initiated accident analysis code for PWR (NODAL3). Nuclear Science and Technology, 6(1), 1-13. https://doi.org/10.53747/jnst.v6i1.139

Status on development and verification of reactivity initiated accident analysis code for PWR (NODAL3)

Peng Hong Liem1, Surian Pinem2, Tagor Malem Sembiring2, Hoai Nam Tran3
1 Nippon Advanced Information Service (NAIS Co., Inc.) 416 Muramatsu, Tokaimura, Ibaraki 319-1112, Japan
2 National Nuclear Energy Agency of Indonesia (BATAN), KawasanPuspiptek Gd. No. 80 Serpong, Tangerang Selatan 15310, Indonesia
3 Institute of Research and Development,Duy Tan University, K7/25 QuangTrung, Da Nang, Vietnam

Main Article Content

Abstract

A coupled neutronics thermal-hydraulics code NODAL3 has been developed based on the nodal few-group neutron diffusion theory in 3-dimensional Cartesian geometry for a typical pressurized water reactor (PWR) static and transient analyses, especially for reactivity initiated accidents (RIA).The spatial variables are treated by using a polynomial nodal method (PNM) while for the neutron dynamic solver the adiabatic and improved quasi-static methods are adopted. A simple single channel thermal-hydraulics module and its steam table is implemented into the code. Verification works on static and transient benchmarks are being conducted to assess the accuracy of the code. For the static benchmark verification, the IAEA-2D, IAEA-3D, BIBLIS and KOEBERG light water reactor (LWR) benchmark problems were selected, while for the transient benchmark verification, the OECD NEACRP 3-D LWR Core Transient Benchmark and NEA-NSC 3-D/1-D PWR Core Transient Benchmark (Uncontrolled Withdrawal of Control Rods at Zero Power). Excellent agreement of the NODAL3 results with the reference solutions and other validated nodal codes was confirmed

Article Details

Keywords

coupled neutronics thermal-hydraulics, nodal method, adiabatic method, improved quasi-static method, PWR, reactivity initiated accident, benchmark verification

References

[1] International Energy Agency, World Energy Outlook 2010.OECD/IEA, Paris, France, 2010.
[2] Presidential Decree of Republic of Indonesia No. 5 Year 2006 on National Energy Policy.
[3] P.H. Liem, “Development and verification of BATAN’s standard two-dimensional multigroup neutron diffusion code (BATAN-2DIFF),” Atom Indonesia, vol. 20, no. 2, pp. 1-19, 1994.
[4] P.H. Liem, “Development of BATAN’s standard 3-D multigroup diffusion code (BATAN-3DIFF)”, Proc. 5-th Workshop of Computation in Nuclear Science and Technology, Batan, Jakarta, Indonesia, 1995.
[5] P.H. Liem, “BATAN-ADJOINT-2D: BATAN's standard code for calculations of integral kinetic parameters of nuclear reactors,” Atom Indonesia, vol. 21, no. 2, pp. 1-18, 1995.
[6] P.H. Liem, “Development and verification of BATAN's standard diffusion code modules for treating triangular mesh geometry,” Atom Indonesia, vol. 24, no. 2, pp. 75-93, 1998.
[7] T.M. Sembiring and P.H. Liem, “Validation of BATAN's standard diffusion codes on IAEA benchmark static calculations,” Atom Indonesia, vol. 23, no. 2, pp. 73-91, 1997.
[8] P.H. Liem and T.M.Sembiring,“Validation of BATAN's standard neutron diffusion codes for control rod worth analysis,” Atom Indonesia, vol. 23, no. 2, pp. 55-72, 1997.
[9] Zuhair, T.M. Sembiring and P.H. Liem, “BATAN-2DIFF and-3DIFF diffusion codes validation on Kyoto University Critical Assembly (KUCA),” Atom Indonesia, vol. 24, no. 1, pp. 15-32, 1998.
[10] P.H. Liem, “Validation of BATAN standard 3-D diffusion code, BATAN-3DIFF, on first core of RSG-GAS,” Atom Indonesia, vol. 25, no. 1, pp. 47-64, 1999.
[11] T.M. Sembiring and P.H. Liem,“Validation of BATAN-3DIFF code on 3-D model of the IAEA 10 MWth benchmark core for partially-inserted control rods,” Atom Indonesia, vol. 25, no. 2, pp. 91-100, 1999.
[12] P.H. Liem,“BATAN-FUEL: A general in-core fuel management code,” Atom Indonesia, vol. 22, no. 2, pp. 67-80, 1996.
[13] P.H. Liem, “Development of an in-core fuel management code for searching equilibrium core in 2-D reactor geometry (BATAN-EQUIL-2D),” Atom Indonesia, vol. 23, no. 1, pp. 1-19, 1997.
[14] P.H.Liem, B. Arbie, T.M. Sembiring, Prayoto and R. Nabbi, “Fuel management strategy for the new equilibrium silicidecore design of RSG GAS (MPR-30),” Nuclear Engineering and Design, 180, pp. 207–219, 1998.
[15] T.M. Sembiring, Tukiran, S. Pinem, Febrianto, “Neutronic design of mixed oxide-silicide cores for the core conversion of RSG-GAS reactor,” Atom Indonesia, vol. 27, no. 2, pp. 85-101, 2001.
[16] S. Pinem and T.M. Sembiring, “Application of neutronics modelling on the transient simulation of RSG-GAS reactor,” Proc. of the International Conference on Mathematics and Natural Science, ITB, Bandung, Indonesia, pp 1056 – 1059, 2006.
[17] S. Pinem and T.M. Sembiring, “Transient analysis of RSG-GAS reactor core for coolant flow reduction using MTR-DYN code,”Journal of Nuclear Reactor Technology Tri Dasa Mega, vol. 11, no. 3, pp. 153 – 161, 2009.
[18] Presidential Regulation of Republic of Indonesia No. 5 Year 2010 on National Medium-Term Development Plan 2010-2014.
[19] R.J.J. Stamm’ler and M. Abbate, Reactor Physics in Nuclear Design. Academic Press, London, England,1983.
[20] H. Finnemann, F. Bennewitz and M.R. Wagner, “Interface current techniques for multidimensional reactorcalculations,” Atomkernenergie, vol. 30, no.2, p.123-128, 1977.
[21] T.M. Sembiring and S. Pinem, ”The validation of the NODAL3 code for static cases of the PWR benchmark core,” Journal of Nuclear Science and Technology Ganendra, vol. 15, no.2, pp. 82-92, 2012.
[22] H. Finnemann and A. Galati,“NEACRP 3-D LWR core transient benchmark. Final specifications,” NEACRP-L-335 (Revision1), 1992.
[23] R. Fraikin, “NEA-NSC 3-D/1-D PWR Core Transient Benchmark Uncontrolled Withdrawal of Control Rods at Zero Power. Final specifications,” NEA/NSC(93)9, 1993.
[24] P.J. Turinsky, “NESTLE: A few-group neutron diffusion equation solver utilizing the nodal expansion method for eigenvalue, adjoint, fix source steady-state and transient problems,” Idaho National engineering Laboratory, EGG-NRE-11406, 1994.
[25] “NODAL3: A Nodal Neutron Diffusion Code, version 2,” User’s Guide, 2010.
[26] K.O. Ott and R.J. Neuhold, Introductory Nuclear Reactor Dynamic, American Nuclear Society, Illinois, USA, 1985.
[27] E.Z. MULLER and E.J. WEISS, Ann. Nucl. Energy, 18, (1991) 535-544
[28]R.R. LEE etal.,Argonne Code Centre: Benchmark Problem Book, Report No.: ANL-7416, Supp. 2, ID.11-A2, Argonne National Laboratory (US), (1977) 277-466
[29]https://engineering.purdue.edu/PARCS/Code/TestSuite/CalculationMode/StandAloneMode/Eigenvalue/IAEA3DPWR/Output/iaea3d.out (2012)
[30] I. Arianiand D. Kastanya, “Evaluation of the IAEA-3D PWR Benchmark Problem Using NESTLE Code,” Prosiding Lokakarya Komputasi Dalam Sains dan Teknologi Nuklir ke-15, PPIN-BATAN, (2005) pp. 20-25.
[31] S. Pinem, T.M. Sembiring and P.H. Liem,“The Verification of Coupled Neutronics Thermal-Hydraulics Code NODAL3 in the PWR Rod Ejection Benchmark,” Science and Technology of Nuclear Installations, 2014.
[32] H. Finnemann, et al.,“Results of LWR core transient benchmark,” NEA/NSC/DOC(93) 25, 1993.
[33] M.P. Knight and P. Bryce,“Derivation of a Refined PANTHER Solution to the NEACRP PWR Rod Ejection Transients,” 1997.
[34] S. Aoki, et al., “The verification of 3-dimensional nodal kinetics code ANCK using transient benchmark problems,” Journal of Nuclear Science and Technology, vol. 44, no. 6, pp. 862–868, 2007.
[35] U. Grundmann and U. Rohde, “Verification of the code DYN3D/R with the help of international benchmarks,” FZR-195, Research Center Rossendorf Inc., Dresden, Germany, 1997.