Scientific design of Purdue University Multi-Dimensional Integral Test Assembly (PUMA) for GE SBWR
- Purdue Univ., Lafayette, IN (United States). School of Nuclear Engineering; and others
The scaled facility design was based on the three level scaling method; the first level is based on the well established approach obtained from the integral response function, namely integral scaling. This level insures that the stead-state as well as dynamic characteristics of the loops are scaled properly. The second level scaling is for the boundary flow of mass and energy between components; this insures that the flow and inventory are scaled correctly. The third level is focused on key local phenomena and constitutive relations. The facility has 1/4 height and 1/100 area ratio scaling; this corresponds to the volume scale of 1/400. Power scaling is 1/200 based on the integral scaling. The time will run twice faster in the model as predicted by the present scaling method. PUMA is scaled for full pressure and is intended to operate at and below 150 psia following scram. The facility models all the major components of SBWR (Simplified Boiling Water Reactor), safety and non-safety systems of importance to the transients. The model component designs and detailed instrumentations are presented in this report.
- Research Organization:
- US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Div. of Systems Technology; Purdue Univ., Lafayette, IN (United States). School of Nuclear Engineering
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- OSTI ID:
- 220555
- Report Number(s):
- NUREG/CR-6309; PU-NE-94/1; ON: TI96009343
- Resource Relation:
- Other Information: PBD: Apr 1996
- Country of Publication:
- United States
- Language:
- English
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