Scaling Analysis of Reactor Cavity Cooling System in HTR

Roberto, Thiago D.; Lapa, Celso Marcelo Franklin; Alvim, A.C.M.

doi:10.1080/00295450.2019.1666603

Cited by 5 publications

(1 citation statement)

References 17 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…The 10-MWth High-temperature gas-cooled Test Reactor (HTR-10) is a helium-cooled and graphite-moderated reactor designed to demonstrate the technical feasibility and safety of the pebble-bed reactor concept [2]. The HTR-10 was designed and constructed at the Nuclear Energy Institute of Technology (INET) of Tsinghua University, Beijing, which reached its first criticality in December 2000 and full capacity of 10 MWth in January 2003 [62]. The HTR-10 plant includes the reactor building, a turbine/generator building, two cooling towers, and a ventilation center and stack.…”

Section: Chinese Htr-10 Water-based Rccsmentioning

confidence: 99%

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

Lisowski¹,

Lv²,

Alexandreanu³

et al. 2021

View full text Add to dashboard Cite

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.

show abstract

Section: Chinese Htr-10 Water-based Rccsmentioning

confidence: 99%