scholarly journals Fluoride-Salt-Cooled High-Temperature Reactor (FHR) for Power and Process Heat

2015 ◽  
Author(s):  
Charles Forsberg ◽  
Lin-wen Hu ◽  
Per Peterson ◽  
Kumar Sridharan
Keyword(s):  
High Temperature ◽  
Fluoride Salt ◽  
High Temperature Reactor ◽  
Process Heat

scholarly journals Process Heat Exchanger Options for Fluoride Salt High Temperature Reactor

2011 ◽  
Author(s):  
Piyush Sabharwall ◽  
Eung Soo Kim ◽  
Michael McKellar ◽  
Nolan Anderson
Keyword(s):  
High Temperature ◽  
Heat Exchanger ◽  
Fluoride Salt ◽  
High Temperature Reactor ◽  
Process Heat

Design evaluation of a small high-temperature reactor for process heat applications

1988 ◽  
Vol 109 (1-2) ◽  
pp. 245-251 ◽  
Author(s):  
Heiko Barnert ◽  
Jasbir Singh
Keyword(s):  
High Temperature ◽  
Design Evaluation ◽  
High Temperature Reactor ◽  
Process Heat

A buoyantly-driven shutdown rod concept for passive reactivity control of a Fluoride salt-cooled High-temperature Reactor

2013 ◽  
Vol 262 ◽  
pp. 600-610 ◽  
Author(s):  
Edward D. Blandford ◽  
Per F. Peterson
Keyword(s):  
High Temperature ◽  
Fluoride Salt ◽  
High Temperature Reactor

scholarly journals Fluoride-Salt-Cooled High-Temperature Reactor (FHR) Using British Advanced Gas-Cooled Reactor (AGR) Refueling Technology and Decay Heat Removal Systems That Prevent Salt Freezing

2019 ◽  
Vol 205 (9) ◽  
pp. 1127-1142 ◽  
Author(s):  
Charles Forsberg ◽  
Dean Wang ◽  
Eugene Shwageraus ◽  
Brian Mays ◽  
Geoff Parks ◽  
...  
Keyword(s):  
High Temperature ◽  
Heat Removal ◽  
Fluoride Salt ◽  
Decay Heat ◽  
High Temperature Reactor

An experimental test facility to support development of the fluoride-salt-cooled high-temperature reactor

2014 ◽  
Vol 64 ◽  
pp. 511-517 ◽  
Author(s):  
Graydon L. Yoder ◽  
Adam Aaron ◽  
Burns Cunningham ◽  
David Fugate ◽  
David Holcomb ◽  
...  
Keyword(s):  
High Temperature ◽  
Experimental Test ◽  
Test Facility ◽  
Fluoride Salt ◽  
High Temperature Reactor

Analysis of thorium and uranium based nuclear fuel options in Fluoride salt-cooled High-temperature Reactor

2015 ◽  
Vol 78 ◽  
pp. 285-290 ◽  
Author(s):  
X.X. Li ◽  
X.Z. Cai ◽  
D.Z. Jiang ◽  
Y.W. Ma ◽  
J.F. Huang ◽  
...  
Keyword(s):  
High Temperature ◽  
Nuclear Fuel ◽  
Fluoride Salt ◽  
High Temperature Reactor

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

2016 ◽  
Vol 2 (3) ◽  
Author(s):  
Kaichao Sun ◽  
Lin-Wen Hu ◽  
Charles Forsberg
Keyword(s):  
High Temperature ◽  
Peak Power ◽  
Fuel Cycle ◽  
Thermal Power ◽  
Combined Cycle ◽  
Fluoride Salt ◽  
Control Rod ◽  
The Core ◽  
Liquid Salt ◽  
High Temperature Reactor

The fluoride-salt-cooled high-temperature reactor (FHR) is a new reactor concept, which combines low-pressure liquid salt coolant and high-temperature tristructural isotropic (TRISO) particle fuel. The refractory TRISO particle coating system and the dispersion in graphite matrix enhance safeguards (nuclear proliferation resistance) and security. Compared to the conventional high-temperature reactor (HTR) cooled by helium gas, the liquid salt system features significantly lower pressure, larger volumetric heat capacity, and higher thermal conductivity. The salt coolant enables coupling to a nuclear air-Brayton combined cycle (NACC) that provides base-load and peak-power capabilities. Added peak power is produced using jet fuel or locally produced hydrogen. The FHR is, therefore, considered as an ideal candidate for the transportable reactor concept to provide power to remote sites. In this context, a 20-MW (thermal power) compact core aiming at an 18-month once-through fuel cycle is currently under design at Massachusetts Institute of Technology (MIT). One of the key challenges of the core design is to minimize the reactivity swing induced by fuel depletion, since excessive reactivity will increase the complexity in control rod design and also result in criticality risk during the transportation process. In this study, burnable poison particles (BPPs) made of B4C with natural boron (i.e., 20% B10 content) are adopted as the key measure for fuel cycle optimization. It was found that the overall inventory and the individual size of BPPs are the two most important parameters that determine the evolution path of the multiplication factor over time. The packing fraction (PF) in the fuel compact and the height of active zone are of secondary importance. The neutronic effect of Li6 depletion was also quantified. The 18-month once-through fuel cycle is optimized, and the depletion reactivity swing is reduced to 1 beta. The reactivity control system, which consists of six control rods and 12 safety rods, has been implemented in the proposed FHR core configuration. It fully satisfies the design goal of limiting the maximum reactivity worth for single control rod ejection within 0.8 beta and ensuring shutdown margin with the most valuable safety rod fully withdrawn. The core power distribution including the control rod’s effect is also demonstrated in this paper.

scholarly journals Sustainability of thorium-uranium in pebble-bed fluoride salt-cooled high temperature reactor

2016 ◽  
Vol 2 ◽  
pp. 8 ◽  
Author(s):  
Guifeng Zhu ◽  
Yang Zou ◽  
Hongjie Xu
Keyword(s):  
High Temperature ◽  
Fluoride Salt ◽  
Pebble Bed ◽  
High Temperature Reactor

Uncertainty analysis of Transportable Fluoride-salt-cooled High-temperature Reactor (TFHR) using coupled DAKOTA with RELAP-3D method

2017 ◽  
Vol 324 ◽  
pp. 269-279 ◽  
Author(s):  
Chenglong Wang ◽  
Kaichao Sun ◽  
Dalin Zhang ◽  
Wenxi Tian ◽  
Suizheng Qiu ◽  
...  
Keyword(s):  
High Temperature ◽  
Uncertainty Analysis ◽  
Fluoride Salt ◽  
High Temperature Reactor
Sign in / Sign up

Export Citation Format

Share Document