A Research Program for Fission Product/Dust Transport in HTGR???s

Loyalka, Sudarshan¹ 

[1]Univ. of Missouri, Columbia, MO (United States)

关键词: NEUTRON ACTIVATION ANALYSIS;    GRAPHITE;    NEUTRON TRANSPORT THEORY;    HTGR TYPE REACTORS;    FISSION PROD;   

DOI  :  10.2172/1242965
RP-ID  :  DOE/NEUP--11-2982
PID  :  OSTI ID: 1242965
Others  :  Other: 11-2982
Others  :  TRN: US1600928

美国|英语

来源: SciTech Connect

【 摘 要 】

High and Very High Temperatures Gas Reactors (HTGRs/VHTRs) have five barriers to fission product (FP) release: the TRISO fuel coating, the fuel elements, the core graphite, the primary coolant system, and the reactor building. This project focused on measurements and computations of FP diffusion in graphite, FP adsorption on graphite and FP interactions with dust particles of arbitrary shape. Diffusion Coefficients of Cs and Iodine in two nuclear graphite were obtained by the release method and use of Inductively Coupled Plasma-Mass Spectroscopy (ICP-MS) and Instrumented Neutron Activation Analysis (INAA). A new mathematical model for fission gas release from nuclear fuel was also developed. Several techniques were explored to measure adsorption isotherms, notably a Knudsen Effusion Mass Spectrometer (KEMS) and Instrumented Neutron Activation Analysis (INAA). Some of these measurements are still in progress. The results will be reported in a supplemental report later. Studies of FP interactions with dust and shape factors for both chain-like particles and agglomerates over a wide size range were obtained through solutions of the diffusion and transport equations. The Green's Function Method for diffusion and Monte Carlo technique for transport were used, and it was found that the shape factors are sensitive to the particle arrangements, and that diffusion and transport of FPs can be hindered. Several journal articles relating to the above work have been published, and more are in submission and preparation.