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RELAP5/MOD3.2 Analysis of INSC Standard Problem INSCSP-V4: Investigation of Heat Transfer for Partly Uncovered VVER-1000 Core at the Test Facility KS (RRC KI).

DE2004822580

Publication Date	2002
Personal Author	Tentner, A. M.; Ahrens, J. W.
Page Count	128
Abstract	The RELAP5/MOD3.2 computer program has been used to analyze a series of tests investigating heat-transfer from a partly uncovered VVER-1000 core in the KS test facility at the Russian Research Center 'Kurchatov Institute' (RRC-KI). The analysis documented represents VVER Standard Problem 4 in Joint Project 6, which is the investigation of Computer Code Validation for Transient Analysis of RBMK and VVER Reactors, between the United States and Russian International Nuclear Safety Centers. The experiment facility and data, RELAP5 nodalization, and results are shown for one of the six tests defined in Standard Problem 4. Only part of the data was analyzed due to our conclusion that the available experimental data is not sufficient to allow the modeling of the actual experiment sequence. The experiment initial conditions were reached through a series of transient processes, about which no quantitative information was available. This has required the modeling of an arbitrary computational transient, with the goal of reaching initial conditions similar to those observed during the experiment. The use of an arbitrary transient introduces many degrees of freedom in the analysis, i.e. initial computational values that influence the entire sequence of events, including the loop behavior during the experiment time window.
Keywords	Heat transfer Radiation protection Sensitivity Computerized simulation Validation Russia Reactor cores R codes Degrees of freedom KS test facility VVER-1000 core WWER type reactors
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	Argonne National Lab., IL.; Department of Energy, Washington, DC.
Supplemental Notes	Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	200501

RELAP5/MOD3.2 Analysis of INSC Standard Problem INSCSP-V4: Investigation of Heat Transfer for Partly Uncovered VVER-1000 Core at the Test Facility KS (RRC KI).

RELAP5/MOD3.2 Analysis of INSC Standard Problem INSCSP-V4: Investigation of Heat Transfer for Partly Uncovered VVER-1000 Core at the Test Facility KS (RRC KI).
DE2004822580

Publication Date	2002
Personal Author	Tentner, A. M.; Ahrens, J. W.
Page Count	128
Abstract	The RELAP5/MOD3.2 computer program has been used to analyze a series of tests investigating heat-transfer from a partly uncovered VVER-1000 core in the KS test facility at the Russian Research Center 'Kurchatov Institute' (RRC-KI). The analysis documented represents VVER Standard Problem 4 in Joint Project 6, which is the investigation of Computer Code Validation for Transient Analysis of RBMK and VVER Reactors, between the United States and Russian International Nuclear Safety Centers. The experiment facility and data, RELAP5 nodalization, and results are shown for one of the six tests defined in Standard Problem 4. Only part of the data was analyzed due to our conclusion that the available experimental data is not sufficient to allow the modeling of the actual experiment sequence. The experiment initial conditions were reached through a series of transient processes, about which no quantitative information was available. This has required the modeling of an arbitrary computational transient, with the goal of reaching initial conditions similar to those observed during the experiment. The use of an arbitrary transient introduces many degrees of freedom in the analysis, i.e. initial computational values that influence the entire sequence of events, including the loop behavior during the experiment time window.
Keywords	Heat transfer Radiation protection Sensitivity Computerized simulation Validation Russia Reactor cores R codes Degrees of freedom KS test facility VVER-1000 core WWER type reactors
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	Argonne National Lab., IL.; Department of Energy, Washington, DC.
Supplemental Notes	Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	200501