Analysis of the Limiting Safety System Settings of a Fluoride Salt–Cooled High-Temperature Test Reactor

Xiao, Yao; Hu, Lin‐Wen; Forsberg, Charles W.; Qiu, Suizheng; Su, G.H.; Chen, Kun; Naxiu, Wang

doi:10.13182/nt13-93

Cited by 16 publications

(7 citation statements)

References 2 publications

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“…For the prismatic core design, the fuel matrix is a cylindrical compact of the TRISO particles. The thermal conductivity of the fuel matrix zone of a pebble and the primatic core cylindrical fuel compacts is k = 1.2768E2 0.06829 − 0.3906E-4 • T dosis + 1.931E-4 • T + 1.228E-4 • T + 0.042 (2.1) where T is in • C, dosis is the fast neutron irradiation dose (10 21 ), and k is in W/m-K for temperatures from 450 to 1300 • C [65,120,166].…”

Section: Fuel Matrix and Graphite Moderationmentioning

confidence: 99%

Fluoride-Salt-Cooled High-Temperature Test Reactor Thermal-Hydraulic Licensing and Uncertainty Propagation Analysis

2019

Nuclear Technology

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An important Fluoride-salt-cooled High-temperature Reactor (FHR) development step is to design, build, and operate a test reactor. Through a literature review, liquid-salt coolant thermophysical properties have been recommended along with their uncertainties of 2-20%. This study tackles determining the effects of these high uncertainties by proposing a newly developed methodology to incorporate uncertainty propagation in a thermalhydraulic safety analysis for test reactor licensing. A hot channel model, Monte Carlo statistical sampling uncertainty propagation, and limiting safety systems settings (LSSS) approach are uniquely combined to ensure sufficient margin to fuel and material thermal limits during steady-state operation and to incorporate margin for high uncertainty inputs. The method calculates LSSS parameters to define safe operation. The methodology has been applied to two test reactors currently considered, the Chinese TMSR-SF1 pebble bed design and MIT's Transportable FHR prismatic core design; two candidate coolants, flibe (LiF-BeF 2) and nafzirf (NaF-ZrF 4); and forced flow and natural circulation conditions to compare operating regions and LSSS power (maximum power not exceeding any thermal limits). The calculated operating region accounts for uncertainty (2σ) with LSSS power (MW) for forced flow of 25.37±0.72, 22.56±1.15, 21.28±1.48, and 11.32±1.35 for pebble flibe, pebble nafzirf, prismatic flibe, and prismatic nafzirf, respectively. The pebble bed has superior heat transfer with an operating region reduced ∼10% less when switching coolants and ∼50% smaller uncertainty than the prismatic. The maximum fuel temperature constrains the pebble bed while the maximum coolant temperature constrains the prismatic due to different dominant heat transfer modes. Sensitivity analysis revealed 1) thermal conductivity and thus conductive heat transfer dominates in the prismatic design while convection is superior in the pebble bed, and 2) the impact of thermophysical property uncertainties are ranked in the following order: thermal conductivity, heat capacity, density, and lastly viscosity. Broadly, the methodology developed incorporates uncertainty propagation that can be used to evaluate parametric uncertainties to satisfy guidelines for non-power reactor licensing applications, and method application shows the pebble bed is more attractive for thermal-hydraulic safety. Although the method was developed and evaluated for coolant property uncertainties for FHR, it is readily applicable for any parameters of interest.

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Section: Fuel Matrix and Graphite Moderationmentioning

confidence: 99%

Fluoride-Salt-Cooled High-Temperature Test Reactor Thermal-Hydraulic Licensing and Uncertainty Propagation Analysis

2019

Nuclear Technology

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“…12 The TRISO fuel particle, from inside to outside, includes a fuel kernel, porous pyrolytic carbon (PyC) buffer, dense inner PyC (IPyC), chemically vapor deposited carbidedsilicon (SiC), and dense outer PyC (OPyC). 13 13 …”

Section: Conceptual Designmentioning

confidence: 99%

“…Figure 5 shows the details of the fuel pebbles, 7 and the geometric parameters are listed in Table 3. 13…”

Section: Conceptual Designmentioning

confidence: 99%

Review of conceptual design and fundamental research of molten salt reactors in China

Zhang

Liu

et al. 2018

Int J Energy Res

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Summary Molten salt reactor (MSR) as 1 candidate of the generation IV advanced nuclear power systems attracted more attention in China due to its top ranked in fuel cycle and thorium utilization. Two types of MSR concepts were studied and developed in parallel, namely the MSR with liquid fuel and that with solid fuel. Abundant fundamental research including the neutronics modeling, thermal‐hydraulics modeling, safety analysis, material investigation, molten salts technologies etc. were carried out. Some analysis software such as COUPLE and FANCY were developed. Several experimental facilities like high‐temperature fluoride salt experiment loop have been constructed. Some passive residual heat removal systems were designed, and 1 test facility is under construction. The key MSR techniques including the extraction and separation of molten salt and construction of N‐base alloy have been mastered. Based on these fundamental research, Chinese Academy of Sciences has completed the design of thorium‐based MSRs with solid fuel and liquid fuel and is promoting their construction in the near future. In China, future efforts should be paid to the material, online fuel processing, Th‐U fuel cycle, component design, and construction and thermal‐hydraulic experiments for MSR, which are rather challenging nowadays.

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“…There is a significant R&D program in China pursing eventual deployment of FHR technology (64). All of these advanced reactor technologies may enable new markets that can reduce the energy sector's GHG emissions and expand applications of nuclear energy, with HTGR and SFR technologies being most promising for deployment by 2035 (49).…”

Section: Nuclear Fissionmentioning

confidence: 99%

The Future of Low-Carbon Electricity

Greenblatt

Brown

Slaybaugh

et al. 2017

Annu. Rev. Environ. Resour.

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We review future global demand for electricity and major technologies positioned to supply it with minimal greenhouse gas (GHG) emissions: renewables (wind, solar, water, geothermal, and biomass), nuclear fission, and fossil power with CO2 capture and sequestration. We discuss two breakthrough technologies (space solar power and nuclear fusion) as exciting but uncertain additional options for low-net GHG emissions (i.e., low-carbon) electricity generation. In addition, we discuss grid integration technologies (monitoring and forecasting of transmission and distribution systems, demand-side load management, energy storage, and load balancing with low-carbon fuel substitutes). For each topic, recent historical trends and future prospects are reviewed, along with technical challenges, costs, and other issues as appropriate. Although no technology represents an ideal solution, their strengths can be enhanced by deployment in combination, along with grid integration that forms a critical set of enabling technologies to assure a reliable and robust future low-carbon electricity system.

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Analysis of the Limiting Safety System Settings of a Fluoride Salt–Cooled High-Temperature Test Reactor

Cited by 16 publications

References 2 publications

Fluoride-Salt-Cooled High-Temperature Test Reactor Thermal-Hydraulic Licensing and Uncertainty Propagation Analysis

Fluoride-Salt-Cooled High-Temperature Test Reactor Thermal-Hydraulic Licensing and Uncertainty Propagation Analysis

Review of conceptual design and fundamental research of molten salt reactors in China

The Future of Low-Carbon Electricity

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