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Preliminary Assessment of Existing Experimental Data for Validation of Reactor Physics Codes and Data for NGNP Design and Analysis.

DE2006861614

Publication Date	2004
Personal Author	Terry, W. K.; Jewell, J. K.; Briggs, J.; Taiwo, T. A.; Park, W. S.
Page Count	76
Abstract	The Next Generation Nuclear Plant (NGNP), a demonstration reactor and hydrogen production facility proposed for construction at the INEEL, is expected to be a high-temperature gas-cooled reactor (HTGR). Computer codes used in design and safety analysis for the NGNP must be benchmarked against experimental data. The INEEL and ANL have examined information about several past and present experimental and prototypical facilities based on HTGR concepts to assess the potential of these facilities for use in this benchmarking effort. Both reactors and critical facilities applicable to pebble-bed and prismatic block-type cores have been considered. Four facilities--HTR-PROTEUS, HTR-10, ASTRA, and AVR--appear to have the greatest potential for use in benchmarking codes for pebble-bed reactors. Similarly, for the prismatic block-type reactor design, two experiments have been ranked as having the highest priority--HTTR and VHTRC.
Keywords	Nuclear reactors Validation Computer codes Construction Design Gas colled reactors Hydrogen production Safety analysis Reactor physics Next Generation Nuclear Plant (NGNP)
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	Argonne National Lab., IL.; Department of Energy, Washington, DC.; Idaho National Engineering Lab., Idaho Falls.
Supplemental Notes	Prepared in cooperation with Idaho National Engineering Lab., Idaho Falls. Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	200615

Preliminary Assessment of Existing Experimental Data for Validation of Reactor Physics Codes and Data for NGNP Design and Analysis.

Preliminary Assessment of Existing Experimental Data for Validation of Reactor Physics Codes and Data for NGNP Design and Analysis.
DE2006861614

Publication Date	2004
Personal Author	Terry, W. K.; Jewell, J. K.; Briggs, J.; Taiwo, T. A.; Park, W. S.
Page Count	76
Abstract	The Next Generation Nuclear Plant (NGNP), a demonstration reactor and hydrogen production facility proposed for construction at the INEEL, is expected to be a high-temperature gas-cooled reactor (HTGR). Computer codes used in design and safety analysis for the NGNP must be benchmarked against experimental data. The INEEL and ANL have examined information about several past and present experimental and prototypical facilities based on HTGR concepts to assess the potential of these facilities for use in this benchmarking effort. Both reactors and critical facilities applicable to pebble-bed and prismatic block-type cores have been considered. Four facilities--HTR-PROTEUS, HTR-10, ASTRA, and AVR--appear to have the greatest potential for use in benchmarking codes for pebble-bed reactors. Similarly, for the prismatic block-type reactor design, two experiments have been ranked as having the highest priority--HTTR and VHTRC.
Keywords	Nuclear reactors Validation Computer codes Construction Design Gas colled reactors Hydrogen production Safety analysis Reactor physics Next Generation Nuclear Plant (NGNP)
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	Argonne National Lab., IL.; Department of Energy, Washington, DC.; Idaho National Engineering Lab., Idaho Falls.
Supplemental Notes	Prepared in cooperation with Idaho National Engineering Lab., Idaho Falls. Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	200615