RCCS Testing with the Water-based NSTF: Year-1 Single-Phase Results

Lisowski, Darius; Lv, Qiuping; Hu, Rui; Kraus, Adam; Bremer, Nathan; Kilsdonk, D. J.; Farmer, M. T.

doi:10.2172/1558600

Cited by 6 publications

(9 citation statements)

References 1 publication

(1 reference statement)

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“…There reduced efficiency, compared to the value of 71% in the previous single-phase tests [7], is mainly due to the increases ambient losses due to higher fluid temperatures and cavity temperatures.…”

Section: Two-phase Baselinementioning

confidence: 61%

“…In total, 370 hours of active test operations were logged across 12 separate test operations. Details of these test cases, including results and observations, can be found in previously published works by the program team [7]. The following sections detail the objectives, completed test cases, and results from the second year of matrix testing.…”

Section: Previous Water Testing Accomplishmentsmentioning

confidence: 99%

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Report on Year-2 of Water NSTF Matrix Testing

Lisowski

Bremer

et al. 2020

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Section: Two-phase Baselinementioning

confidence: 61%

Section: Previous Water Testing Accomplishmentsmentioning

confidence: 99%

Report on Year-2 of Water NSTF Matrix Testing

Lisowski

Bremer

et al. 2020

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“…Several aspects of NSTF, such as geometry and dimensions of the riser tubes and cooling fin test section, heated plate set back distance, etc., were determined with direct involvement from industry partners. The resulting as-built facility reflects a 1:2 axial scale and 12.5° sector slice of the primary design for their full-scale concept [82].…”

Section: Air-cooled Rccsmentioning

confidence: 99%

“…Based on recent results published by the water-based NSTF program [82], baseline testing was conducted that reflect conditions prototypic to the full-scale plant at both normal operation and design basis DLOFC conditions. These parameters translated to NSTF scaled thermal power levels of 34.4 kWt and 51.6 kWt, respectively.…”

Section: Air-cooled Rccsmentioning

confidence: 99%

“…With continued development and further understanding, engineering controls or design features can then be incorporated to allow these systems to operate only in stable regimes. In an attempt to answer these questions, accelerometers were used to measure the structural vibrations present in an operating 1:2 scale water-based RCCS [82]. The authors indicate that the data is preliminary, and continued development may provide valuable insight into the stability and performance expected from a fullscale installation.…”

Section: Structural Vibrations From System Oscillationsmentioning

confidence: 99%

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An Overview of Non-LWR Vessel Cooling Systems for Passive Decay Heat Removal (Technical Letter Final Report)

Lisowski¹,

Lv²,

Alexandreanu³

et al. 2021

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The following report provides a technical review of various reactor vessel cooling system (VCS) concepts under consideration for decay heat removal (DHR) in non-light water advanced reactor designs. This review focuses on ex-vessel designs, including the Reactor Cavity Cooling System (RCCS), the Reactor Vessel Auxiliary Cooling System (RVACS), and hybrid iterations, using both air and water cooling to achieve their heat removal function. Based on a literature review of publicly available sources published between 1979 and 2021, a technical summary is presented detailing existing and planned VCS design options, their applicability to specific reactor type, and review of authored research and development studies. Following an assessment of the availability of data and modeling tools, an evaluation was performed analyzing their likely performance during normal, degraded, and accident conditions, including reliability, stability, and longevity.With renewed consideration of air-based DHR systems by some US vendors, there is a need to fully understand the complexities inherent to natural circulation systems, and more importantly, how they may influence safety-related heat removal functions and system performance. For DHR systems that rely on air-based mode of cooling, this entails quantification of the impacts of low flow conditions during start-up, relative elevations of inlet and outlet ducts for below-grade installations, effects of the use of multiple parallel chimneys for redundancy, and impact of weather conditions at the plant site. For systems relying on water-based mode cooling, reliance on limited coolant inventory in an event of pipe break or extended duration accident scenarios, sensitivities related to stability of boiling flow and heat transfer conditions, and quantification of full-scale structural vibrations on balance of plant structures are among the complicating factors. Paperwork Reduction Act StatementThis report does not contain information collection requirements and, therefore, is not subject to the requirements of the Paperwork Reduction Act of 1995 (44 United States Code [U.S.C.] 3501 et seq.). Public Protection NotificationThe U.S. Nuclear Regulatory Commission (NRC) may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a current valid Office of Management and Budget (OMB) control number.

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Design of a prototypical natural circulation water-based reactor cavity cooling system (RCCS) for a pebble-bed generic FHR

Talaat

Chen

2023

Nuclear Engineering and Design

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RCCS Testing with the Water-based NSTF: Year-1 Single-Phase Results

Cited by 6 publications

References 1 publication

Report on Year-2 of Water NSTF Matrix Testing

Report on Year-2 of Water NSTF Matrix Testing

An Overview of Non-LWR Vessel Cooling Systems for Passive Decay Heat Removal (Technical Letter Final Report)

Design of a prototypical natural circulation water-based reactor cavity cooling system (RCCS) for a pebble-bed generic FHR

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