VALIDATION OF FULL CORE GEOMETRY MODEL OF THE NODAL3 CODE IN THE PWR TRANSIENT BENCHMARK PROBLEMS
DOI:
https://doi.org/10.17146/tdm.2015.17.3.2322Keywords:
nodal method, coupled neutronic and thermal-hydraulic code, PWR, transient case, control rod ejectionAbstract
VALIDATION OF FULL CORE GEOMETRY MODEL OF THE NODAL3 CODE IN THE PWR TRANSIENT BENCHMARK PROBLEMS. The coupled neutronic and thermal-hydraulic (T/H) code, NODAL3 code, has been validated in some PWR static benchmark and the NEACRP PWR transient benchmark cases. However, the NODAL3 code have not yet validated in the transient benchmark cases of a control rod assembly (CR) ejection at peripheral core using a full core geometry model, the C1 and C2 cases. By this research work, the accuracy of the NODAL3 code for one CR ejection or the unsymmetrical group of CRs ejection case can be validated. The calculations by the NODAL3 code have been carried out by the adiabatic method (AM) and the improved quasistatic method (IQS). All calculated transient parameters by the NODAL3 code were compared with the reference results by the PANTHER code. The maximum relative difference of 16% occurs in the calculated time of power maximum parameter by using the IQS method, while the relative difference of the AM method is 4% for C2 case. All calculation results by the NODAL3 code shows there is no systematic difference, it means the neutronic and T/H modules are adopted in the code are considered correct. Therefore, all calculation results by using the NODAL3 code are very good agreement with the reference results.
References
Aoki S, Suemura T, Ogawa J, Takeda T. The Verification of 3 Dimensional Nodal Kinetics Code ANCK Using Transient Benchmark Problems. 2007;44(6):862-8.
https://doi.org/10.1080/18811248.2007.9711323
Jiménez J, Cuervo D, Aragonés JM. A domain decomposition methodology for pin by pin coupled neutronic and thermal - hydraulic analyses in COBAYA3. Nucl. Eng. Design 2010;240:313-20.
https://doi.org/10.1016/j.nucengdes.2009.01.012
Barrachina T, Garcia-fenoll M, Ánchel F, Miró R, Verdú G, Pereira C, et al. REA 3D dynamic analysis in Almaraz NPP with RELAP5 / PARCS v2.7 and SIMTAB cross-sections tables. Prog. Nucl. Energy 2011;53(8):1167-80.
https://doi.org/10.1016/j.pnucene.2011.07.012
Aghaie M, Zolfaghari A, Minuchehr A. Coupled neutronic thermal - hydraulic transient analysis of accidents in PWRs. Ann. Nucl. Energy 2012;50:158-66.
https://doi.org/10.1016/j.anucene.2012.07.013
Grgic D, Bencik V, Sadek S. Coupled code calculation of rod withdrawal at power accident. Nucl. Eng. Design 2013;261:285-305.
https://doi.org/10.1016/j.nucengdes.2012.10.026
Lianjie W, Wenbo Z, Bingde C, Dong Y, Ping Y. Development of three dimensional transient analysis code STTA for SCWR core. Ann. Nucl. Energy 2015;78:26-32.
https://doi.org/10.1016/j.anucene.2014.12.025
Calleja M, Jimenez J, Sanchez V, Imke U, Stieglitz R, Macián R. Investigations of boron transport in a PWR core with COBAYA3/SUBCHANFLOW inside the NURESIM platform. Ann. Nucl. Energy 2014;66:74-84.
https://doi.org/10.1016/j.anucene.2013.11.034
Pinem S, Sembiring TM, Liem PH. The Verification of Coupled Neutronics Thermal Hydraulics Code NODAL3 in the PWR Rod Ejection Benchmark. Science and Technology of Nuclear Installations 2014; 2014.
https://doi.org/10.1155/2014/845832
Sembiring T.M, Pinem S. The validation of the NODAL3 code for static cases of the PWR benchmark core. Journal of Nuclear Science and Technology GANENDRA 2012;15:82-92.
https://doi.org/10.17146/gnd.2012.15.2.18
Finnemann H, Galati A. Paris: NEACRP 3-D LWR core transient benchmark-final specifications. OECD Nuclear Energy Agency; 1992 Jan. 75 p. NEACRP-L-335 (Revision 1).
Finnemann H, Bauer H, Galati A, Martinelli R. Paris: Results of LWR core transient benchmarks. OECD Nuclear Energy Agency; 1993 Oct. 80 p. NEA/NSC/ DOC(93)25.
