Fission product holdup in graphite. [HTGR]

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Multicomponent time-dependent concentration diffusion and radioactive decay of isotopic species is an important aspect of fission product migration and release from fuel particles and fuel elements in a High Temperature Gas-Cooled Reactor (HTGR). After fission products escape from a fuel particle in an HTGR, it is still necessary for them to diffuse across the graphite web of a fuel block to a coolant hole before they can be entrained in the primary coolant. The time required for a given fission product species to diffuse across the graphite web has a direct influence on the time-dependent release associated with a significant ... continued below

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Pages: 10

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Apperson, C. Jr.; Carruthers, L.M. & Anderson, C.A. January 1, 1978.

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Description

Multicomponent time-dependent concentration diffusion and radioactive decay of isotopic species is an important aspect of fission product migration and release from fuel particles and fuel elements in a High Temperature Gas-Cooled Reactor (HTGR). After fission products escape from a fuel particle in an HTGR, it is still necessary for them to diffuse across the graphite web of a fuel block to a coolant hole before they can be entrained in the primary coolant. The time required for a given fission product species to diffuse across the graphite web has a direct influence on the time-dependent release associated with a significant increase in the power/flow ratio. The main purpose of the paper is to present the results of a study of the holdup time in graphite of Sr as a function of the diffusion constants. The study employs a newly-developed multicomponent time-dependent diffusion and decay code called DASH. Analysis methods for solving the type of problem discussed are well known, and some applications to fission product decay and diffusion in HTGRs have appeared in the literature. However, the methods employed are often subject to time step limitations, and the effects of decay are not adequately handled. The DASH code uses a one dimensional spatial discretization for the diffusion operator and an analytic matrix operator method to remove the time dependence. Comparisons of the solutions given by DASH with a number of analytic solutions have been made, and in all instances considered the agreement with analytical solutions is excellent and limited only by the inaccuracy inherent in the spatial discretization.

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Pages: 10

Notes

Dep. NTIS, PC A02/MF A01.

Source

  • 2. US-Japan seminar on HTGR safety technology, Fuji, Japan, 24 Nov 1978

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  • Report No.: LA-UR-78-2931
  • Report No.: CONF-781144-2
  • Grant Number: W-7405-ENG-36
  • Office of Scientific & Technical Information Report Number: 6349287
  • Archival Resource Key: ark:/67531/metadc1208473

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

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Creation Date

  • January 1, 1978

Added to The UNT Digital Library

  • July 5, 2018, 11:11 p.m.

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  • Sept. 21, 2018, 5:46 p.m.

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Apperson, C. Jr.; Carruthers, L.M. & Anderson, C.A. Fission product holdup in graphite. [HTGR], article, January 1, 1978; United States. (digital.library.unt.edu/ark:/67531/metadc1208473/: accessed November 13, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.