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Title: Assessment of Candidate Molten Salt Coolants for the NGNP/NHI Heat-Transfer Loop

Abstract

This report provides an assessment of candidate salts proposed as the coolant for the loop that shuttles heat from the Next Generation Nuclear Plant (NGNP) to the Nuclear Hydrogen Initiative (NHI) hydrogen-production plant. The physical properties most relevant for coolant service were reviewed, and key chemical factors that influence material compatibility were also analyzed for the purpose of screening candidate salts. A preliminary assessment of the cost of the raw materials required to produce the coolant is also presented. Salts that are suitable for use as the primary coolant in a high-temperature nuclear reactor were previously analyzed. Some of the fluoride salts identified in the previous study are also appropriate for consideration as the secondary coolant in a heat-transfer loop; therefore, results from the previous report are used in this document. However, alternative coolant salts (i.e., chlorides and fluoroborates) that were not considered in the previous report should be considered for service in the heat-transfer loop. These alternative coolants are considered in this report.

Authors:
 [1]
  1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1360677
Report Number(s):
ORNL/TM-2006/69
DOE Contract Number:  
AC05-00OR22725
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS

Citation Formats

Williams, D. F. Assessment of Candidate Molten Salt Coolants for the NGNP/NHI Heat-Transfer Loop. United States: N. p., 2006. Web. doi:10.2172/1360677.
Williams, D. F. Assessment of Candidate Molten Salt Coolants for the NGNP/NHI Heat-Transfer Loop. United States. https://doi.org/10.2172/1360677
Williams, D. F. 2006. "Assessment of Candidate Molten Salt Coolants for the NGNP/NHI Heat-Transfer Loop". United States. https://doi.org/10.2172/1360677. https://www.osti.gov/servlets/purl/1360677.
@article{osti_1360677,
title = {Assessment of Candidate Molten Salt Coolants for the NGNP/NHI Heat-Transfer Loop},
author = {Williams, D. F.},
abstractNote = {This report provides an assessment of candidate salts proposed as the coolant for the loop that shuttles heat from the Next Generation Nuclear Plant (NGNP) to the Nuclear Hydrogen Initiative (NHI) hydrogen-production plant. The physical properties most relevant for coolant service were reviewed, and key chemical factors that influence material compatibility were also analyzed for the purpose of screening candidate salts. A preliminary assessment of the cost of the raw materials required to produce the coolant is also presented. Salts that are suitable for use as the primary coolant in a high-temperature nuclear reactor were previously analyzed. Some of the fluoride salts identified in the previous study are also appropriate for consideration as the secondary coolant in a heat-transfer loop; therefore, results from the previous report are used in this document. However, alternative coolant salts (i.e., chlorides and fluoroborates) that were not considered in the previous report should be considered for service in the heat-transfer loop. These alternative coolants are considered in this report.},
doi = {10.2172/1360677},
url = {https://www.osti.gov/biblio/1360677}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Jun 30 00:00:00 EDT 2006},
month = {Fri Jun 30 00:00:00 EDT 2006}
}