573
Views
0
CrossRef citations to date
0
Altmetric
Article

Hydrogen flux through the heat transfer tube wall in the steam generator of Monju

&
Pages 343-349 | Received 12 Feb 2013, Accepted 11 Nov 2013, Published online: 16 Dec 2013

References

  • Roy P, Rodgers DN. Hydrogen burden from the steam side corrosion in sodium-heated steam generators. Nucl Technol. 1978;39:213–215.
  • Tomlinson L, Cory NJ. Hydrogen emission during the steam oxidation of ferritic steels: kinetics and mechanism. Corros Sci. 1989;29:939–965.
  • Cory NJ, Herrington TM, Tomlinson L. Hydrogen emission during the steam oxidation of ferritic steels: experimental technique. Corros Sci. 1988;28:333–342.
  • Iizawa K, Torii T. Hydrogen and tritium behaviour in Monju; validation of an analysis code for tritium transport in fast reactor system, TTT, and estimation for Monju full power operation in future. Japan: Japan Nuclear Fuel Cycle Development Institute; 1999. Japanese.
  • Iizawa K, Torii T. Development of a tritium transport analysis code for the LMFBR system. Japan: Japan Nuclear Fuel Cycle Development Institute; 2001. Japanese.
  • Vissers DR. A hydrogen activity meter for liquid sodium and its application to hydrogen solubility measurements. Nucl Technol. 1974;21:235–244.
  • Gwyther JR, Whittingham AC. The kinetics of hydrogen removal from liquid sodium. In: Borgstedt HU, editor. Material behavior and physical chemistry in liquid metal systems. New York (NY): Plenum Press; 1982. p. 335–343.
  • Rohrig HD, Hecker R, Blumensaat J, Schaefer J. Studies on the permeation of hydrogen and tritium in nuclear process heat installations. Nucl Eng Des. 1975;34:157–167.
  • Gilbert ER, Allen RP, Baldwin DL, Bell RD, Brimhall JL. Tritium permeation and related studies on barrier treated 316 stainless steel. Fusion Technol. 1992;21:739–744.
  • Hollenberg GW, Simonen EP, Kalinin G, Terlain A. Tritium/hydrogen barrier development. Fusion Eng Des. 1995;28:190–208.
  • Nei H. Hydrogen behavior in FBR secondary cooling system. J At Energy Soc Jpn. 1979;21:405–410. Japanese.
  • Kaneko Y, Nishikimi M, Shirato S, Tsuchiya T, Fukuda T. Experiments on the water leak detection systems in the 50MW Steam Generator Test Facility -9-; cold trap efficiency test, hydrogen background, concentration test, hydrogen flux through tube test. Japan: Power Reactor and Nuclear Fuel Development Corporation; 1985. Japanese.
  • The Cold Trap Study Group. Hydrogen behavior and removal in sodium cooled fast breeder reactor. Japan: Power Reactor and Nuclear Fuel Development Corporation; 1980. Japanese.
  • Nuclear Power Technology Development Section. Fast reactor database 2006 update. Vienna: International Atomic Energy Agency; 2007.
  • Paterson SR, Moser R, Rettig TR. The oxidation of boiler tubes. Proceedings of the International Conference on Interaction of Iron-Based Materials with Water and Steam; 1992 June 3–5; Heidelberg, Germany.
  • Chang PL, Bennett WDG. Diffusion of hydrogen in iron and iron alloys at elevated temperatures. J Iron Steel Inst. 1952;179:205–213.

Reprints and Corporate Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

To request a reprint or corporate permissions for this article, please click on the relevant link below:

Academic Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

Obtain permissions instantly via Rightslink by clicking on the button below:

If you are unable to obtain permissions via Rightslink, please complete and submit this Permissions form. For more information, please visit our Permissions help page.