Libros sobre el tema "Nuclear reactors – Computer simulation"

Puska, Eija Karita. Nuclear reactor core modelling in multifunctional simulators. Espoo [Finland]: Technical Research Centre of Finland, 1999.

Klein, M. E. Simulation of in-reactor experiments with the ELOCA.Mk5 code. Chalk River, Ont: Chalk River Laboratories, 1994.

Kim, K. Assessment of RELAP5/MOD2 critical flow model using Marviken test data 15 and 24. Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1992.

Kim, Kyu-Soo. Assessment of RELAP5/MOD2 critical flow model using Marviken test data 15 and 24. Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1992.

Mayya, Y. S. Containment aerosol behaviour simulation studies in the BARC nuclear aerosol test facility. Mumbai: Bhabha Atomic Research Centre, 2005.

Hämäläinen, A. Applying thermal hydraulics modeling in coupled processes of nuclear power plants. [Espoo, Finland]: VTT Technical Research Centre of Finland, 2005.

Ross, Kyle. MELCOR best practices as applied in the State-of-the-Art Reactor Consequence Analyses (SOARCA) Project. Washington, DC: U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2014.

Llopis, C. Assessment of RELAP5/MOD3.2-NPA3.4 against an inadvertent closure of all three MSIV's in VANDELLOS-II nuclear power plant. Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2001.

Weingardt, Jay J. TAC2D studies of Mark I containment drywell shell melt-through. Washington, DC: Division of Reactor Accident Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1988.

Analytis, G. Th. Assessment of interfacial shear and wall heat transfer of RELAP5/MOD2/36.02 during reflooding. Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989.

Dosanjh, S. S. Relocation of metallic constituents in core debris beds. Washington, DC: Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1988.

Carlson, Don. Assessment of databases and modeling capabilities for the CANDU 3 design. Washington, DC: Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1994.

Llopis, C. Assessment of RELAP5/MOD3.2-NPA3.4 against an inadvertent closure of all three MSIV's in VANDELLOS-II nuclear power plant. Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2001.

Llopis, C. Assessment of RELAP5/MOD3.2-NPA3.4 against an inadvertent closure of all three MSIV's in VANDELLOS-II nuclear power plant. Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2001.

Llopis, C. Assessment of RELAP5/MOD3.2-NPA3.4 against an inadvertent closure of all three MSIV's in VANDELLOS-II nuclear power plant. Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2001.

Llopis, C. Assessment of RELAP5/MOD3.2-NPA3.4 against an inadvertent closure of all three MSIV's in VANDELLOS-II nuclear power plant. Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2001.

Wilson, T. L. Hydrogen mixing studies (HMS): Theory and computational model. Washington, DC: Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1992.

Klein, M. E. Simulation of in-reactor experiments with the ELOCA.Mk5 code. Chalk River, Ont: Fuel Engineering Branch, Chalk River Laboratories, 1994.

Kullberg, Craig M. RELAP5 thermal-hydraulic analysis of the SNUPPS pressurized water reactor. Washington, DC: Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1990.

Kullberg, Craig M. RELAP5 thermal-hydraulic analysis of the SNUPPS pressurized water reactor. Washington, DC: Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1990.

U.S. Nuclear Regulatory Commission. Modeling potential reactor accident consequences. Washington, D.C: U.S. Nuclear Regulatory Commission, 2012.

Bixler, N. E. MACCS best practices as applied in the State-of-the-Art Reactor Consequence Analyses (SOARCA) Project. Washington, DC: U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2014.

Wang, Jong-Rong. The development and assessment of TRACE model for Maanshan Nuclear Power Plant LOCA. Washington, DC: U. S. Nuclear Regulatory Commission, 2012.

U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. y Lappeenrannan teknillinen korkeakoulu. Energiatekniikan laitos., eds. Assessment study on the PMK-2 total loss of feedwater experiment using RELAP5 code. Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2001.

Won, Seul Kwang, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research y Hanʾguk Wŏnjaryŏk Anjŏn Kisurwŏn. Advanced Reactor Dept, eds. Assessment of RELAP5/MOD3.2 with the LSTF experiment simulating a loss of residual heat removal event during mid-loop operation. Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1998.

U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research y Lappeenrannan teknillinen korkeakoulu. Energiatekniikan laitos, eds. Assessment study on the PMK-2 total loss of feedwater experiment using RELAP5 code. Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2001.

Assessment of the turbine trip transient in Cofrentes NPP with TRAC-BF1. Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1993.

A, Gomez, Gallego I, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. y Unidad Eléctrica S. A, eds. Assessment of the turbine trip transient in Cofrentes NPP with TRAC-BF1. Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1993.

Ma, Chang Chun. Study of interfacial condensation in a nuclear reactor core makeup tank. 1993.

M, Bowman S., U.S. Nuclear Regulatory Commission. Division of Fuel Cycle Safety and Safeguards. y Oak Ridge National Laboratory, eds. KENO3D visualization tool for KENO V.a and KENO-VI geometry models. Washington, DC: Division of Fuel Cycle Safety and Safeguards, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, 2000.

Assessment of MSIV full closure for Santa Maria De Garon a nuclear power plant using TRAC-BF1 (G1J1). Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1993.

L, Rebollo, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. y Unio n. Ele ctrica-Fenosa, eds. Assessment of RELAP5/MOD2 against a pressurizer spray valve inadverted fully opening transient and recovery by natural circulation in Jose Cabrera nuclear station. Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1993.

M, Martin, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research y Pablo Moreno SA, eds. Assessment of RELAP5/MOD3.2-NPA3.4 against a transient of high nuclear flux variation reactor trip, natural circulation and the start of a main pump in the VANDELLOS II nuclear power plant. Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1998.

Assessment of RELAP5/MOD3.2-NPA3.4 against a transient of high nuclear flux variation reactor trip, natural circulation and the start of a main pump in the VANDELLOS II nuclear power plant. Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1998.

M, Martin, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. y Pablo Moreno SA, eds. Assessment of RELAP5/MOD3.2-NPA3.4 against a transient of high nuclear flux variation reactor trip, natural circulation and the start of a main pump in the VANDELLOS II nuclear power plant. Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1998.

Assessment of RELAP5/MOD3.2-NPA3.4 against a transient of high nuclear flux variation reactor trip, natural circulation and the start of a main pump in the VANDELLOS II nuclear power plant. Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1998.

M, Martin, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research y Pablo Moreno SA, eds. Assessment of RELAP5/MOD3.2-NPA3.4 against a transient of high nuclear flux variation reactor trip, natural circulation and the start of a main pump in the VANDELLOS II nuclear power plant. Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1998.

M, Martin, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research y Pablo Moreno SA, eds. Assessment of RELAP5/MOD3.2-NPA3.4 against a transient of high nuclear flux variation reactor trip, natural circulation and the start of a main pump in the VANDELLOS II nuclear power plant. Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1998.

W, Ambrosini, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research, Autoridad Regulatoria Nuclear (Argentina) y Università di Pisa. Dipartimento di costruzioni meccaniche e nucleari, eds. Verification of RELAP5/MOD 3 with theoretical and numerical stability results on single-phase, natural circulation in a simple loop. Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1999.

W, Ambrosini, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research., Autoridad Regulatoria Nuclear (Argentina) y Università di Pisa. Dipartimento di costruzioni meccaniche e nucleari., eds. Verification of RELAP5/MOD 3 with theoretical and numerical stability results on single-phase, natural circulation in a simple loop. Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1999.

F, Lozano M., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research y Pablo Moreno SA, eds. Assessment of a reactor coolant pump trip for TRILLO NPP with RELAP5/MOD3.2. Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2000.

A, Fernández R., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. y Universidad de Cantabria, eds. Assessment of MSIV full closure for Santa Maria De Garoña nuclear power plant using TRAC-BF1 (G1J1). Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1993.

Ans. Proceedings Nuclear Thermal Hydraulics, 1990 (Order No 2700156). Amer Nuclear Society, 1990.

Ans. Proceedings Nuclear Thermal Hydraulics, 1989 (Order No 2700148). Amer Nuclear Society, 1989.

Analysis of the LOBI experiment test BT-56 using the RELAP5/MOD3.2 code. Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2000.

U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Systems Technology. y Oak Ridge National Laboratory, eds. LAPUR benchmark against in-phase and out-of-phase stability tests. Washington, DC: Division of Systems Technology, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1990.

An implicit steady-state initialization package for the RELAP5 computer code. Washington, D.C: Division of Systems Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1995.

J, García García, López Montero J. V, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. y NUCLENOR S. A, eds. Assessment of single recirculation pump trip transient in Santa Maria de Garona Nuclear Power Plant with TRAC-BF1/MOD1, version 0.4. Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2001.

Assessment of single recirculation pump trip transient in Santa Maria de Garona Nuclear Power Plant with TRAC-BF1/MOD1, version 0.4. Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2001.

Assessment of single recirculation pump trip transient in Santa Maria de Garona Nuclear Power Plant with TRAC-BF1/MOD1, version 0.4. Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2001.