
doi: 10.2172/7099198
A review of the RELAP5/MOD2 computer code has been performed to assess the basis for the models and correlations comprising the code. The review has included verification of the original data base, including thermodynamic, thermal-hydraulic, and geothermal conditions; simplifying assumptions in implementation or application; and accuracy of implementation compared to documented descriptions of each of the models. An effort has been made to provide the reader with an understanding of what is in the code and why it is there and to provide enough information that an analyst can assess the impact of the correlation or model on the ability of the code to represent the physics of a reactor transient. Where assessment of the implemented versions of the models or correlations has been accomplished and published, the assessment results have been included.
570, Equations, Nonbreeding, Nonboiling Water Cooled, Hydraulics, Fluid Mechanics, 21 Specific Nuclear Reactors And Associated Plants, Mechanics, 530, Reactor Accidents, Reactor Cooling Systems, Transients, Differential Equations, Energy Systems, Evaluation, Reactor Components, Light-Water Moderated, R Codes, 22 General Studies Of Nuclear Reactors, Reactor Safety, Computer Codes, Mathematical Models, Pwr Type Reactors, Cooling Systems, Heat Transfer, Reactors, Energy Transfer, Accidents, Flow Models, Water Cooled Reactors, 210200 -- Power Reactors, Safety, Water Moderated Reactors 220900* -- Nuclear Reactor Technology-- Reactor Safety
570, Equations, Nonbreeding, Nonboiling Water Cooled, Hydraulics, Fluid Mechanics, 21 Specific Nuclear Reactors And Associated Plants, Mechanics, 530, Reactor Accidents, Reactor Cooling Systems, Transients, Differential Equations, Energy Systems, Evaluation, Reactor Components, Light-Water Moderated, R Codes, 22 General Studies Of Nuclear Reactors, Reactor Safety, Computer Codes, Mathematical Models, Pwr Type Reactors, Cooling Systems, Heat Transfer, Reactors, Energy Transfer, Accidents, Flow Models, Water Cooled Reactors, 210200 -- Power Reactors, Safety, Water Moderated Reactors 220900* -- Nuclear Reactor Technology-- Reactor Safety
| selected citations These citations are derived from selected sources. This is an alternative to the "Influence" indicator, which also reflects the overall/total impact of an article in the research community at large, based on the underlying citation network (diachronically). | 9 | |
| popularity This indicator reflects the "current" impact/attention (the "hype") of an article in the research community at large, based on the underlying citation network. | Top 10% | |
| influence This indicator reflects the overall/total impact of an article in the research community at large, based on the underlying citation network (diachronically). | Top 10% | |
| impulse This indicator reflects the initial momentum of an article directly after its publication, based on the underlying citation network. | Average |
