Surrogate Models for TREAT Transient Calculations
- Nuclear Engineering Methods Development, Idaho National Laboratory, Idaho Falls, ID 83415 (United States)
- Reactor Physics Design and Analysis, Idaho National Laboratory, Idaho Falls, ID 83415 (United States)
The Transient Reactor Test Facility (TREAT) at Idaho National Laboratory (INL) is currently preparing for resumption of operation after more than 20 years in a long-term standby state. In parallel with preparation for operations and a new transient testing program, the DOENE Advanced Modeling and Simulation program (NEAMS) has been supporting the development of three-dimensional transient multi-physics modeling capabilities within the reactor physics application MAMMOTH. Recently, the MAMMOTH reactor physics team has begun development of uncertainty and sensitivity analysis for the TREAT core. This research will be used to support the analysis of reactor operation and experiment planning. Traditional approaches, i.e., Monte Carlo simulations, for such tasks require a large number of model evaluations under both steady state and transient conditions. However, exhaustive sets of sampling runs are simply not practical for TREAT since evaluations of each model can take a substantial amount of time. A solution to this problem is to build a surrogate model employing a smaller number of model evaluations. The surrogate model is designed to provide an accurate and fast approximation to the detailed TREAT model. In this manner, the surrogate model can be used in place of the TREAT transient model for uncertainty and sensitivity analysis at a fraction of the computational cost. The high dimensional model representation (HDMR) method is employed here for approximating the responses of interest in terms of functions of lower dimensions. This method has been implemented in RAVEN and all TREAT transient calculations are performed using the multiphysics code MAMMOTH. In addition, a code interface has also been developed in order to couple RAVEN with MAMMOTH. The surrogate model is then tested and compared for TREAT startup testing program Transient Test no. 15 core, and its accuracy is measured by its ability to estimate the mean, coefficient of variance, skewness, excess kurtosis and probability density function of the outputs of Transient Test no. 15 model, as well as root mean square error metric.
- OSTI ID:
- 23050337
- Journal Information:
- Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 116; ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
97 MATHEMATICS AND COMPUTING
ACCURACY
ASYMMETRY
COMPUTERIZED SIMULATION
DESIGN
ERRORS
EXPERIMENT PLANNING
IDAHO NATIONAL LABORATORY
MONTE CARLO METHOD
PROBABILITY DENSITY FUNCTIONS
REACTOR OPERATION
REACTOR PHYSICS
SAMPLING
SENSITIVITY ANALYSIS
STEADY-STATE CONDITIONS
TESTING
THREE-DIMENSIONAL CALCULATIONS
TRANSIENTS
TREAT REACTOR