Search Menu
DOE PAGES title logo U.S. Department of Energy
Office of Scientific and Technical Information
Search Scholarly Publications

Title: Advanced heat exchanger development for molten salts

Abstract

This study addresses present work concerned with advanced heat exchanger development for molten salt in nuclear and non nuclear thermal systems. The molten salt systems discussed herein use alloys, such as Hastelloy N and 242, which show corrosion resistance to molten salt at nominal operating temperatures up to 700°C. These alloys were diffusion welded, and the corresponding information is presented. Test specimens were prepared for exposing diffusion welds to molten salt environments. Hastelloy N and 242 were found to be weldable by diffusion welding, with ultimate tensile strengths about 90% of base metal values. Both diffusion welds and sheet material in Hastelloy N were corrosion tested in?58 mol% KF and 42 mol% ZrF4 at 650, 700, and 850°C for 200, 500, and 1,000 hours. Corrosion rates found were similar between welded and nonwelded materials, typically <10 mils per year. For materials of construction, nickel and alloys with dense nickel coatings are effectively inert to corrosion in fluorides, but not so in chlorides. Hence, additional testing of selected alloys for resistance to intergranular corrosion is needed, as is a determination of corrosion rate as a function of contaminant type and alloy composition with respect to chromium and carbon to better definemore » the optimal chromium and carbon composition, independent of galvanic or differential solubility effects. Also presented is the division of the nuclear reactor and high temperature components per ASME standards, along with design requirements for a subcritical Rankine power cycle heat exchanger that has to overcome pressure difference of about 17 MPa.« less

Authors:
 [1];  [1];  [1];  [2];  [2];  [2]
+ Show Author Affiliations
  1. Idaho National Lab. (INL), Idaho Falls, ID (United States)
  2. Univ. of Wisconsin, Madison, WI (United States)
Publication Date:
Research Org.:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1162199
Report Number(s):
INL/JOU-13-30397
Journal ID: ISSN 0029-5493
Grant/Contract Number:  
DE-AC07-05ID14517
Resource Type:
Accepted Manuscript
Journal Name:
Nuclear Engineering and Design
Additional Journal Information:
Journal Volume: 280; Journal Issue: C; Journal ID: ISSN 0029-5493
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
42 ENGINEERING; HASTELLOY 242; HASTELLOY N ALLOYS

Citation Formats

Sabharwall, Piyush, Clark, Denis, Glazoff, Michael, Zheng, Guiqiu, Sridharan, Kumar, and Anderson, Mark. Advanced heat exchanger development for molten salts. United States: N. p., 2014. Web. doi:10.1016/j.nucengdes.2014.09.026.
Copy to clipboard
Sabharwall, Piyush, Clark, Denis, Glazoff, Michael, Zheng, Guiqiu, Sridharan, Kumar, & Anderson, Mark. Advanced heat exchanger development for molten salts. United States. https://doi.org/10.1016/j.nucengdes.2014.09.026
Copy to clipboard
Sabharwall, Piyush, Clark, Denis, Glazoff, Michael, Zheng, Guiqiu, Sridharan, Kumar, and Anderson, Mark. Mon . "Advanced heat exchanger development for molten salts". United States. https://doi.org/10.1016/j.nucengdes.2014.09.026. https://www.osti.gov/servlets/purl/1162199.
Copy to clipboard
@article{osti_1162199,
title = {Advanced heat exchanger development for molten salts},
author = {Sabharwall, Piyush and Clark, Denis and Glazoff, Michael and Zheng, Guiqiu and Sridharan, Kumar and Anderson, Mark},
abstractNote = {This study addresses present work concerned with advanced heat exchanger development for molten salt in nuclear and non nuclear thermal systems. The molten salt systems discussed herein use alloys, such as Hastelloy N and 242, which show corrosion resistance to molten salt at nominal operating temperatures up to 700°C. These alloys were diffusion welded, and the corresponding information is presented. Test specimens were prepared for exposing diffusion welds to molten salt environments. Hastelloy N and 242 were found to be weldable by diffusion welding, with ultimate tensile strengths about 90% of base metal values. Both diffusion welds and sheet material in Hastelloy N were corrosion tested in?58 mol% KF and 42 mol% ZrF4 at 650, 700, and 850°C for 200, 500, and 1,000 hours. Corrosion rates found were similar between welded and nonwelded materials, typically <10 mils per year. For materials of construction, nickel and alloys with dense nickel coatings are effectively inert to corrosion in fluorides, but not so in chlorides. Hence, additional testing of selected alloys for resistance to intergranular corrosion is needed, as is a determination of corrosion rate as a function of contaminant type and alloy composition with respect to chromium and carbon to better define the optimal chromium and carbon composition, independent of galvanic or differential solubility effects. Also presented is the division of the nuclear reactor and high temperature components per ASME standards, along with design requirements for a subcritical Rankine power cycle heat exchanger that has to overcome pressure difference of about 17 MPa.},
doi = {10.1016/j.nucengdes.2014.09.026},
journal = {Nuclear Engineering and Design},
number = C,
volume = 280,
place = {United States},
year = {Mon Dec 01 00:00:00 EST 2014},
month = {Mon Dec 01 00:00:00 EST 2014}
}
Copy to clipboard
Journal Article:
Free Publicly Available Full Text
Publisher's Version of Record
https://doi.org/10.1016/j.nucengdes.2014.09.026
Copyright Statement
Other availability
Search WorldCat Search WorldCat to find libraries that may hold this journal
Citation Metrics:
Cited by: 30 works
Citation information provided by
Web of Science

Figures / Tables:

Figure 1 Figure 1: Advanced energy system using process heat.
All figures and tables (21 total)
Save / Share:
Export Metadata
Save to My Library
You must Sign In or Create an Account in order to save documents to your library.

Works referenced in this record:

Experience with the Molten-Salt Reactor Experiment
journal, February 1970

  • Haubenreich, Paul N.; Engel, J. R.
  • Nuclear Applications and Technology, Vol. 8, Issue 2
  • DOI: 10.13182/NT8-2-118

Corrosion characteristics of reduced activation ferritic steel, JLF-1 (8.92Cr–2W) in molten salts Flibe and Flinak
journal, June 2009

Metallurgical study on corrosion of austenitic steels in molten salt LiF–BeF2 (Flibe)
journal, April 2009

New Developments in Materials for Molten-Salt Reactors
journal, February 1970

  • McCoy, H. E.; Beatty, R. L.; Cook, W. H.
  • Nuclear Applications and Technology, Vol. 8, Issue 2
  • DOI: 10.13182/NT70-A28622

Chemical behavior of Li2BeF4 molten salt as a liquid tritium breeder
journal, November 2001

Materials corrosion in molten LiF–NaF–KF salt
journal, January 2009

Corrosion of metals by molten salts in heat-treatment processes
journal, March 1985

  • Ozeryanaya, I. N.
  • Metal Science and Heat Treatment, Vol. 27, Issue 3
  • DOI: 10.1007/BF00699649

JUPITER-II molten salt Flibe research: An update on tritium, mobilization and redox chemistry experiments
journal, February 2006

  • Petti, David A.; Smolik, G. R.; Simpson, Michael F.
  • Fusion Engineering and Design, Vol. 81, Issue 8-14, p. 1439-1449
  • DOI: 10.1016/j.fusengdes.2005.08.101

Engineering design elements of a two-phase thermosyphon for the purpose of transferring NGNP thermal energy to a hydrogen plant
journal, November 2009

Diffusion-Welded Microchannel Heat Exchanger for Industrial Processes
journal, March 2013

  • Sabharwall, Piyush; Clark, Denis E.; Mizia, Ronald E.
  • Journal of Thermal Science and Engineering Applications, Vol. 5, Issue 1
  • DOI: 10.1115/1.4007578

Diffusion of titanium in modified hastelloy N
journal, July 1969

    Sort by:
    [ × clear filter / sort ]

    Works referencing / citing this record:

      Sort by:
      [ × clear filter / sort ]

      Figures / Tables found in this record:

      Figure 1 (p. 3)figure
      Table 1 (p. 5)table
      Figure 2 (p. 7)figure
      Table 2 (p. 10)table
      Table 3 (p. 14)table
      Table 4 (p. 14)table
      Figure 3 (p. 16)figure
      Figure 4 (p. 17)figure
      Figure 5 (p. 18)figure
      Figure 6 (p. 18)figure
      Table 5 (p. 23)table
      Figure 7 (p. 26)figure
      Figure 8 (p. 26)figure
      Figure 9 (p. 26)figure
      Figure 10 (p. 27)figure
      Figure 11 (p. 27)figure
      Figure 12 (p. 29)figure
      Figure 13 (p. 29)figure
      Figure 14 (p. 31)figure
      Figure 15 (p. 32)figure
      Figure 16 (p. 33)figure
        [ × clear filter / sort ]
        Figures/Tables have been extracted from DOE-funded journal article accepted manuscripts.

        Similar Records in DOE PAGES and OSTI.GOV collections: