International Code Assessment and Applications Program: Summary of code assessment studies concerning RELAP5/MOD2, RELAP5/MOD3, and TRAC-B. International Agreement Report
International Code Assessment and Applications Program: Summary of code assessment studies concerning RELAP5/MOD2, RELAP5/MOD3, and TRAC-B. International Agreement Report
Members of the International Code Assessment Program (ICAP) have assessed the US Nuclear Regulatory Commission (USNRC) advanced thermal-hydraulic codes over the past few years in a concerted effort to identify deficiencies, to define user guidelines, and to determine the state of each code. The results of sixty-two code assessment reviews, conducted at INEL, are summarized. Code deficiencies are discussed and user recommended nodalizations investigated during the course of conducting the assessment studies and reviews are listed. All the work that is summarized was done using the RELAP5/MOD2, RELAP5/MOD3, and TRAC-B codes.
- University of North Texas United States
Loss Of Coolant, International Cooperation, Eccs, Boiling Water Cooled, Nonbreeding, Nonboiling Water Cooled, Hydraulics, 21 Specific Nuclear Reactors And Associated Plants, Coordinated Research Programs, Reactor Cooling Systems, T Codes 220900, Evaluation, Light-Water Moderated, R Codes, 22 General Studies Of Nuclear Reactors, Reactor Safety, Computing, Pwr Type Reactors, 600, Heat Transfer, Bwr Type Reactors, 99 General And Miscellaneous//Mathematics, Mathematics And Computers, Power Reactors, Nuclear Power Plants, And Information Science, 210200, 210100, 990200
Loss Of Coolant, International Cooperation, Eccs, Boiling Water Cooled, Nonbreeding, Nonboiling Water Cooled, Hydraulics, 21 Specific Nuclear Reactors And Associated Plants, Coordinated Research Programs, Reactor Cooling Systems, T Codes 220900, Evaluation, Light-Water Moderated, R Codes, 22 General Studies Of Nuclear Reactors, Reactor Safety, Computing, Pwr Type Reactors, 600, Heat Transfer, Bwr Type Reactors, 99 General And Miscellaneous//Mathematics, Mathematics And Computers, Power Reactors, Nuclear Power Plants, And Information Science, 210200, 210100, 990200
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