Evaluation of strontium-90 radial concentration profiles in Peach Bottom HTGR Core 2 fuel elements. HTGR base technology program, HTGR chemistry studies (189a 01329). [483 2000]

Technical Report · Thu Feb 01 00:00:00 EST 1979

DOI:https://doi.org/10.2172/6223309· OSTI ID:6223309

Haire, M J

Radial concentration profiles of /sup 90/Sr were evaluated for four fuel elements of the Peach Bottom High-Temperature Gas-Cooled Reactor (HTGR) Core 2. A transport model utilizing a single effective diffusion coefficient was able to reproduce the strontium concentraion profile in graphite at temperatures above about 960/sup 0/C. Below this temperature, ''tails'' were observed in the experimental concentration profile and the profiles could not be completely reproduced. Diffusion coefficients determined from the study were slightly below those used in current reference HTGR design calculations. Experimental data exhibited a relatively high concentration at the graphite surfaces. Data and analyses are presented which indicate this may be due to a spatial variation in graphite properties resulting from an inhomogeneous distribution of the graphite impregnant. Unlike earlier Peach Bottom Core 1 studies the /sup 90/Sr precursor contribution to the total /sup 90/Sr concentration profile was determined to be negligible for these Core 2 data, apparently due to the much lower fuel partial coating failure fraction in Core 2. The calculated /sup 90/Sr released from the core is less than that measured, but the amount released is well below the amount established by design criteria.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 6223309
• Report Number(s): ORNL/TM-6209; GJBX-6(79); TRN: 79-007671
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
PEACH BOTTOM-1 REACTOR
FUEL ELEMENTS
DIFFUSION
FISSION PRODUCT RELEASE
FISSION PRODUCTS
GRAPHITE
PERMEABILITY
QUANTITY RATIO
RADIOACTIVITY TRANSPORT
REACTOR CORES
SPATIAL DISTRIBUTION
STRONTIUM 90
ALKALINE EARTH ISOTOPES
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
CARBON
DISTRIBUTION
ELEMENTS
ENRICHED URANIUM REACTORS
EVEN-EVEN NUCLEI
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HELIUM COOLED REACTORS
HTGR TYPE REACTORS
INTERMEDIATE MASS NUCLEI
ISOTOPES
NONMETALS
NUCLEI
POWER REACTORS
RADIOACTIVE MATERIALS
RADIOISOTOPES
REACTOR COMPONENTS
REACTORS
STRONTIUM ISOTOPES
THERMAL REACTORS
YEARS LIVING RADIOISOTOPES
210300* - Power Reactors
Nonbreeding
Graphite Moderated