scholarly journals Certification plan for reactor analysis computer codes

1990 ◽  
Author(s):  
H. Toffer ◽  
R.D. Crowe ◽  
K.N. Schwinkendorf ◽  
R.E. Pevey
Keyword(s):  
Analysis Computer ◽  
Computer Codes

Computation of Force Traces for the Rolamite

1971 ◽  
Vol 93 (1) ◽  
pp. 47-52 ◽  
Author(s):  
R. V. Cadman
Keyword(s):  
Energy Analysis ◽  
Experimental Results ◽  
Analysis Computer ◽  
Computer Codes ◽  
Geometry Analysis

Rolamite geometries having rectangular and diamond cutouts are presented as examples illustrating the use of the geometry analysis computer codes for accurately predicting force traces. The resultant traces are quite different from those predicted by the simple energy analysis, and agree well with experimental results.

Systematic Qualification of the Coupled Neutron Transport and Thermal-Hydraulics Code DORT-TD/THERMIX

2008 ◽  
Author(s):  
Bismark Tyobeka ◽  
Andreas Pautz ◽  
Kostadin Ivanov
Keyword(s):  
Neutron Transport ◽  
Benchmark Problems ◽  
Coupling Scheme ◽  
Thermal Hydraulics ◽  
Comparison Of Results ◽  
Nuclear Systems ◽  
Analysis Computer ◽  
Computer Codes ◽  
Plant Data ◽  
Comparison Of The Results

In order to present credible results in nuclear design and safety analysis, computer codes must adhere to stringent qualification procedures imposed by nuclear licensing authorities. Such procedures form the basis for a quality assured verification and validation process. This is particularly true for advanced nuclear systems of Generation IV type, where little licensing experience exists as well as little or no plant data is available. Qualification of nuclear design and analysis codes can be achieved in various ways, namely: comparison of results from a code with results from another code i.e. code to code benchmarking; comparison of results from a given code with experimental results, i.e. code to experiment benchmarking; comparison of results from a given code with operational plant data; and finally, comparison of the results of a given code with known analytical solutions. In this paper, a systematic qualification of the coupled neutron transport and thermal hydraulics code DORT-TD/THERMIX is presented. As part of developing this coupled code to the level where it can be used as an independent tool by both designers of pebble-bed High-Temperature Gas-cooled Reactors (HTGRs) and regulators, an effort has been made to verify the coupling scheme as well as the validity of application for this code package. At these initial stages a code to code comparison has been adopted as the qualification method of choice. This is done for both steady-state and transient benchmark problems, ranging from simplified to detailed models. As shown in the results section, all benchmarks have been successfully recalculated and generally show good to very good agreement with the “reference” solutions.

Seal Analysis Computer Codes

1994 ◽  
Author(s):  
Wilbur Shapiro ◽  
Mahesh M. Athavale
Keyword(s):  
Analysis Computer ◽  
Computer Codes

Integral Testing of the AP600 Passive Emergency Core Cooling Systems

1993 ◽  
Vol 207 (4) ◽  
pp. 259-268 ◽  
Author(s):  
L E Hochreiter ◽  
S V Fanto ◽  
L E Conway ◽  
L K Lau
Keyword(s):  
Natural Circulation ◽  
Cooling Mode ◽  
Passive Safety Systems ◽  
Pressure Test ◽  
Integral Systems ◽  
Analysis Computer ◽  
Computer Codes ◽  
Core Cooling ◽  
Safety Systems

In support of the development of AP600, Westinghouse is conducting two integral systems tests to examine the performance of the passive safety systems. A full-height, full-pressure test is being performed to simulate a small loss-of-coolant, steam generator tube rupture and large steam line break events. A one-quarter scale, low-pressure test is being performed to simulate transients with emphasis on the transition to the natural circulation post-accident, long-term cooling mode and to demonstrate the long-term cooling capability. Each of the tests will provide detailed experimental results for verification of the accident analysis computer codes.

scholarly journals Verification and validation plan for reactor analysis computer codes

1989 ◽  
Author(s):  
H. Toffer ◽  
R.D. Crowe ◽  
K.N. Schwinkendorf ◽  
R.E. Pevey
Keyword(s):  
Verification And Validation ◽  
Validation Plan ◽  
Analysis Computer ◽  
Computer Codes

scholarly journals Verification and validation plan for reactor analysis computer codes

1989 ◽  
Author(s):  
H. Toffer ◽  
R.D. Crowe ◽  
K.N. Schwinkendorf ◽  
R.E. Pevey
Keyword(s):  
Verification And Validation ◽  
Validation Plan ◽  
Analysis Computer ◽  
Computer Codes

Structural Dynamic Analysis of Wind Turbine Systems

1982 ◽  
Vol 104 (2) ◽  
pp. 89-95 ◽  
Author(s):  
R. W. Thresher
Keyword(s):  
Experimental Data ◽  
Dynamic Analysis ◽  
Natural Frequencies ◽  
Cyclic Loads ◽  
Current Analysis ◽  
Structural Dynamic ◽  
Horizontal Axis Wind Turbines ◽  
Analysis Computer ◽  
Computer Codes ◽  
Major Emphasis

The paper presents an overview of the dynamic analysis of horizontal axis wind turbines. The major emphasis of the paper is the review of current analysis methods and the comparison of results with experimental data. The current capabilities for predicting turbine system natural frequencies are discussed and the design implications of frequency placement are reviewed. The prediction of cyclic loads, using the dynamic analysis computer codes, is examined and comparisons are made between the code predictions and field test data. Finally, the dynamic analysis needs for advanced turbine systems are considered.

A Finite-Element Method Applied to the Vibration of Submerged Plates

1978 ◽  
Vol 22 (02) ◽  
pp. 94-99 ◽  
Author(s):  
Melvyn S. Marcus
Keyword(s):  
Finite Element ◽  
Finite Element Approach ◽  
Liquid Free Surface ◽  
Basic Fluid ◽  
Vibrating Plates ◽  
Analysis Computer ◽  
Element Approach ◽  
Computer Codes ◽  
Propeller Blades ◽  
Acoustic Fluid

A finite-element approach is used to simulate the free vibration of submerged cantilever plates. The method explicitly models an acoustic fluid with pressure as the basic fluid unknown. Only standard capabilities of structural analysis computer codes such as NASTRAN are required for implementation. The computations performed take into account liquid free surface and partial submergence effects. The numerical results obtained compare favorably with experimentally measured frequencies of vibrating plates. Modeling requirements are discussed. Application areas include the vibration in water of rudders, propeller blades, and other ship appendages.

Analysis of Thermal Transients for sCO2 Brayton Cycle Heat Exchangers

2019 ◽  
Author(s):  
Anton Moisseytsev ◽  
James J. Sienicki
Keyword(s):  
Heat Exchanger ◽  
Heat Exchangers ◽  
Thermal Loading ◽  
Power Converter ◽  
System Level ◽  
Normal Operation ◽  
Brayton Cycle ◽  
Thermal Transients ◽  
Analysis Computer ◽  
Computer Codes

Abstract The design of heat exchangers for use in a supercritical carbon dioxide (sCO2) Brayton cycle power converter must provide for acceptable performance for duty cycle events encompassing anticipated transients and postulated accidents. This paper presents the results of a comprehensive analysis of thermal transients for sCO2 cycle heat exchangers, with emphasis on the sodium-to-CO2 heat addition heat exchanger. A range of transients, from normal operation to severe accidents, were simulated with the coupled PDC and SAS4A/SASSYS-1 system level dynamic analysis computer codes. For each transient, the calculated change in the heat exchanger wall temperature is determined as a measure of the thermal loading.

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