Monte Carlo based core parameter validation for a uranium-aluminide-fueled test reactor
Conference
·
OSTI ID:459255
- Idaho National Engineering Lab., Idaho Falls, ID (United States)
A complete three-dimensional MCNP full-core model of the uranium-aluminide-fueled Advanced Test Reactor has been developed. The limited core parameter validation was performed through comparison of the fuel element and lobe power distributions as well as core multiplication factors to the available measured data. The MCNP full-core model accurately predicted critical eigenvalue for different critical outer shim settings. The predictions of the fuel element and lobe powers were reasonably good when compared to the measured data, and to the PDQ results. Application of the Monte Carlo based full-core model is broad, and includes reactivity effect study of experiment loading, neutron and gamma flux calculations in various capsule and loop irradiation facilities, radiation heating rate analysis, power generation in fuel elements, and isotope production rate analysis.
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 459255
- Report Number(s):
- CONF-950420--
- Country of Publication:
- United States
- Language:
- English
Similar Records
Three-dimensional PDQ validation for calculating core parameters of a uranium-aluminide-fueled test reactor
Validation of HELIOS for ATR Core Follow Analyses
MCNP full-core modeling of the advanced test reactor
Journal Article
·
Fri Mar 31 23:00:00 EST 1995
· Nuclear Technology
·
OSTI ID:46137
Validation of HELIOS for ATR Core Follow Analyses
Conference
·
Sat Feb 28 19:00:00 EST 2015
·
OSTI ID:1177209
MCNP full-core modeling of the advanced test reactor
Conference
·
Thu Dec 31 23:00:00 EST 1992
· Transactions of the American Nuclear Society; (United States)
·
OSTI ID:5882147