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Journal of Nuclear Science and Technology Volume 54, 2017 - Issue 8
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Article

Validation of 3D neutronic-thermalhydraulic coupled codes RELAP5/PARCSv2.7 and TRACEv5.0P3/PARCSv3.0 against a PWR control rod drop transient

Marina Garcia-FenollInstitute for Industrial, Radiophysical and Environmental Safety, Universitat Politècnica de València, Valencia, Spain
,
Carles MesadoInstitute for Industrial, Radiophysical and Environmental Safety, Universitat Politècnica de València, Valencia, Spain
,
Teresa BarrachinaInstitute for Industrial, Radiophysical and Environmental Safety, Universitat Politècnica de València, Valencia, Spain
,
Rafael MiróInstitute for Industrial, Radiophysical and Environmental Safety, Universitat Politècnica de València, Valencia, SpainCorrespondence[email protected]
,
Gumersindo VerdúInstitute for Industrial, Radiophysical and Environmental Safety, Universitat Politècnica de València, Valencia, Spain
,
Juan Antonio BermejoIberdrola Ingeniería y Construcción, Nuclear Generation Department, Madrid, Spain
,
Arturo LópezIberdrola Ingeniería y Construcción, Nuclear Generation Department, Madrid, Spain
&
Alberto OrtegoCentrales Nucleares Almaraz y Trillo, Nuclear Design Deparment, Madrid, Spain
 show all
Pages 908-919 | Received 19 May 2016, Accepted 06 Apr 2017, Published online: 29 May 2017

References

  • Miró R, Verdú G, Sánchez AM, et al. Analysis of a rod withdrawal accident in a BWR with the neutronic-thermalhydraulic coupled code TRAC-BF1/VALKIN and TRACE/PARCS. PHYSOR-2006. 2006;43:1511–1519
  • Barrachina T, Garcia-Fenoll M, Ánchel F, et al. REA 3D-dynamic analysis in Almaraz NPP with RELAP5/PARCS v2.7 and SIMTAB cross-sections tables. Prog Nucl Energ. 2011;53:1167–1180.
  • Ánchel F, Barrachina T, Miró R, et al. Uncertainty and sensitivity analysis in the neutronic parameters generation for BWR and PWR coupled thermalhydraulic–neutronic simulations. Nucl Eng Design. 2012;246:98–106.
  • High Burnup Fuel PIRT Panel. Phenomena identification and ranking tables (PIRTs) for Rod Ejection Accidents in Pressurized Water Reactors Containing High Burnup Fuel, Los Alamos (NM): Los Alamos National Laboratory. 2001.
  • U. S. NRC. Standard Review Plan. Chapter 15.0 Introduction -Transient and Accident Analysis. NUREG-0800.Washington (DC): U. S. Nuclear Regulatory Commission. 1987.
  • MATLAB and Statistics Toolbox Release. The MathWorks S.L. Natick (MA); 2013.
  • Ortego A, Modelo CN. Trillo mediante los códigos CASMO-4/SIMULATE-3 [Trillo NPP model with CASMO-4/SIMULATE-3]. Madrid (Spain): Centrales Nucleares Almaraz y Trillo. 2004.
  • Tochihara H, Ochiai E, Hasegawa T. Re-evaluation of spatial weighting factors for EX-CORE neutron detectors. Nucl Technol. 1982;15:310–317.
  • Simulación de CN. Trillo con RELAP5 módulo YC - vasija del reactor [RELAP5 Trillo NPP simulation - YC module - reactor vessel]. Madrid (Spain): Centrales Nucleares Almaraz y Trillo. 2002.
  • Mesado C, Barrachina T, Miró R, et al. PWR simulation using a 3D vessel with TRACE/PARCS. The 15th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, NURETH-15; 2013 May 12–17; Pisa, Italy.
  • Mesado C, García-Fenoll M, Miró R, et al. Modelado de un PWR mediante componentes 3D [PWR model with 3D components]. 39º Reunión anual de la sociedad nuclear española. Reus: SNE. 2013; p. 25–27.
  • Roselló O. Desarrollo de una metodología de generación de secciones eficaces para la simplificación del núcleo de reactores de agua ligera y aplicación en códigos acoplados neutrónico/termohidráulicos [Development of a metholodogy for cross section generation for LWR core simplification and its aplication to neutronic/thermal-hydraulic coupled codes]. [PhD thesis]. València (Spain): Universitat Politècnica de València.2004.
  • RELAP5/MOD3.3 code manual. Volume IV: models and correlations. Washington (DC): U. S. Nuclear Regulatory Commission. 2001.
  • Groeneveld DC, Leung LKH, Kirillov PL, et al. The 1995 look-up table for critical heat flux in tubes. Nucl Eng Design. 1996;163:1–23.
  • TRACE v5.0 Theory Manual. Field equations, solution methods and physical models. Washington (DC): U. S. Nuclear Regulatory Commission. 2012.
  • Groeneveld DC, Cheng SC, Doan T. AECL-UP critical heat flux lookup table. Heat Transfer Eng. 1986;7:46–62.
  • Bermejo JA, Encinas L, López A, et al. Análisis de fluctuaciones termohidráulicas en C. N. Trillo con SIMULATE-3K [Thermal-hydraulic fluctuations analyses with SIMLATE-3K at Trillo NPP]. 38ª Reunión anual de la sociedad nuclear española. Cáceres: SNE. 2012; p. 17–19.

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