Fluoride-Salt-Cooled High-Temperature Test Reactor Thermal-Hydraulic Licensing and Uncertainty Propagation Analysis-Reference-Cited by-同舟云学术

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

Published:2019-06-05 Issue:11 Volume:205 Page:1495-1512
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Romatoski R. R.¹²^ORCID,Hu L. W.¹³^ORCID

Affiliation:

1. Massachusetts Institute of Technology, Nuclear Engineering Department, 77 Massachusetts Avenue, Cambridge, Massachusetts 02139

2. St. Ambrose University, Engineering and Physics Department, 518 West Locust Street, Davenport, Iowa 52803

3. Massachusetts Institute of Technology, Nuclear Reactor Laboratory, 77 Massachusetts Avenue, Cambridge, Massachusetts 02139

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.1080/00295450.2019.1610686

Reference36 articles.

1. C. W. FORSBERG et al. “Fluoride-Salt-Cooled High-Temperature Reactors (FHRs) for Base-Load and Peak Electricity, Grid Stabilization, and Process Heat,” CANES MIT-ANP-TR-147, Massachusetts Institute of Technology Center for Advanced Nuclear Energy Systems (2013).

2. Basis for Fluoride Salt–Cooled High-Temperature Reactors with Nuclear Air-Brayton Combined Cycles and Firebrick Resistance-Heated Energy Storage

3. Fluoride salt coolant properties for nuclear reactor applications: A review

4. Neutronics modeling and analysis of the TMSR-SF1 fuel lattice and full core with explicit fuel particle distribution and random pebble loadings

5. Neutronic Design Features of a Transportable Fluoride-Salt-Cooled High-Temperature Reactor

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