High Pressure Post-CHF Rod Bundle Tests Program or High Pressure Post-CHF Rod Bundle Tests Program

The U.S. Nuclear Regulatory Commission (NRC) proposes to enter into a non-competitive indefinite delivery-indefinite quantity type contract with the Pennsylvania State University (PSU) for the project entitled, "High Pressure Post-CHF Rod Bundle Tests Program". The proposed period of performance for this contract is a five year base period. The statutory authority permitting Other Than Full and Open Competition is 41 U.S.C. 253(c)(1), as implemented by FAR 6.302-1 (b)(1), which provides for limiting competition in those situations where the services are available from only one responsible source and no other type of services will satisfy NRC's requirements. The designated North American Industry Classification System (NAICS) Code NAICS Code is 541712, Research and Development in the Physical, Engineering, and Life Sciences (except Biotechnology), with a size standard of 500 employees. The objective of this work is to: (1) obtain experimental two-phase heat transfer data for high pressure post-CHF film boiling conditions; (2) design and manufacture a new test apparatus that is suitable for high temperature, high pressure reflood tests and quick changes of various types of spacer grids; (3) develop heat transfer model and correlations for reactor safety code validation and assessment; (4) experiment with direct flow field parameter measurements using gamma tomography; and (5) create a pilot version of the TRACE code with the new models and correlations developed from the new data. To accomplish the above stated objectives for this project, the contractor must have: (1) detailed knowledge of two-phase flow theory and experimental techniques, (2) demonstrated experience and expertise in multi-phase instrumentation and measurement skills; (3) a dedicated test facility, with power supply and Data Acquisition System ready to connect to the high pressure bundle (up to 1000 psia) to be constructed under this proposed program, (4) a boiler and water supply system that is capable of supplying a reflood rate of 10 in/sec for 20 minutes continuously at high steam pressure(up to 1000 psia); (5) a power supply that can convert 1 Megawatt AC to 750 kw DC (12600 Amp 60VDC minimum with an extremely low ripple effect (0.05%)) capable of heating the fuel simulators to a temperature of 2200 degrees F, and (6) a test cell with proper radiation shielding and safety features that can accommodate gamma ray experiments for direct measurement of void in the rod bundle. The purpose of this proposed research program is to obtain high quality post-CHF rod bundle heat transfer data for reactor safety computer code assessment and validation. The configuration of rod bundle and spacer grid is expected to be generic, therefore the data could be applied to a broader user base. It is this reason that NRC does not wish to receive bids from private fuel vendors with their proprietary design configurations. Specifically, this new facility will model a portion of the fuel bundle (i.e., one or two sections of the fuel bundle, where a section is a portion of the bundle between two spacer grids) in the reactor core and has the capability to supply pressurized and heated steam and water to the high temperature rod bundle to simulate various reflood conditions. This is not a request for competitive proposals. Request for copies of this solicitation will not be honored unless the respondent provides evidence showing their capability to perform the required services. Detailed capabilities must be submitted to Mr. Rob Robinson, Contract Specialist via e-mail at richard.robinsonii@nrc.gov no later than February 10, 2017 (i.e. 15 calendar days from the date this announcement was posted). Inquiries regarding this announcement may be made to Rob Robinson, Contract Specialist by phone at (301) 415-0728 or via e-mail at richard.robinsonii@nrc.gov.