scholarly journals EXPERIMENTAL TEST OF THE FREVAP-8 CODE FOR CALCULATING METAL FISSION PRODUCT RELEASE FROM HTGR FUEL ELEMENTS.

1968 ◽  
Author(s):  
H.J. de Nordwall ◽  
V.H. Pierce ◽  
L.R. Zumwalt
Keyword(s):  
Fission Product ◽  
Experimental Test ◽  
Product Release ◽  
Fuel Elements ◽  
Htgr Fuel

Fission Product Release From HTGR Fuel Under Core Heatup Accident Conditions

2008 ◽  
Author(s):  
Karl Verfondern ◽  
Heinz Nabielek
Keyword(s):  
Fission Product ◽  
Technology Development ◽  
Normal Operation ◽  
Fuel Performance ◽  
Heating Facility ◽  
Product Release ◽  
Essential Input ◽  
Accident Conditions ◽  
Product Species ◽  
Htgr Fuel

Various countries engaged in the development and fabrication of modern fuel for the High Temperature Gas-Cooled Reactor (HTGR) have initiated activities of modeling the fuel and fission product release behavior with the aim of predicting the fuel performance under operating and accidental conditions of future HTGRs. Within the IAEA directed Coordinated Research Project CRP6 on “Advances in HTGR Fuel Technology Development” active since 2002, the 13 participating Member States have agreed upon benchmark studies on fuel performance during normal operation and under accident conditions. While the former has been completed in the meantime, the focus is now on the extension of the national code developments to become applicable to core heatup accident conditions. These activities are supported by the fact that core heatup simulation experiments have been resumed recently providing new, highly valuable data. Work on accident performance will be — similar to the normal operation benchmark — consisting of three essential parts comprising both code verification that establishes the correspondence of code work with the underlying physical, chemical and mathematical laws, and code validation that establishes reasonable agreement with the existing experimental data base, but including also predictive calculations for future heating tests and/or reactor concepts. The paper will describe the cases to be studied and the calculational results obtained with the German computer model FRESCO. Among the benchmark cases in consideration are tests which were most recently conducted in the new heating facility KUEFA. Therefore this study will also re-open the discussion and analysis of both the validity of diffusion models and the transport data of the principal fission product species in the HTGR fuel materials as essential input data for the codes.

Postirradiation Testing of High Temperature Reactor Spherical Fuel Elements Under Accident Conditions

2010 ◽  
Vol 132 (4) ◽  
Author(s):  
D. Freis ◽  
D. Bottomley ◽  
J. Ejton ◽  
W. de Weerd ◽  
H. Kostecka ◽  
...  
Keyword(s):  
High Temperature ◽  
Fission Product ◽  
Fission Products ◽  
General Concept ◽  
Cold Finger ◽  
Product Release ◽  
High Temperature Reactor ◽  
Accident Conditions ◽  
Fuel Elements ◽  
Beijing China

A new furnace for accident condition testing of spherical high temperature reactor fuel elements has been installed and now operates in the hot cells of the Institute for Transuranium Elements (ITU) Karlsruhe. The recent apparatus was constructed on the basis of a former development by Forschungszentrum Jülich (Schenk, Pitzer, and Nabielek, 1988, “Fission Product Release Profiles From Spherical HTR Fuel Elements at Accident Temperatures,” Jülich Report No. 2234), where it was named KüFA, the German acronym for cold finger apparatus. In a preceding publication (Kostecka, Ejton, de Weerd, and Toscano, 2004, “Post-Irradiation Testing of HTR-Fuel Elements Under Accident Conditions, Part 1 and 2,” Second International Topical Meeting on High Temperature Reactor Technology, Beijing, China) the general concept and details of the device were described. The present paper reports on the first operation under hot conditions, and the calibration of the fission gas measurement and of the efficiency of the cold finger, which is used to plate out solid fission products. Finally the results of fission product release and analysis of two heating tests on two fuel elements from the high temperature reactor K6 irradiation experiment (Nabielek, Conrad, Roellig, and Meyers, 1993, “Fuel Irradiation Experiments on HFR-K6 and HFR-B1 With Intermittent Water Vapour Injections,” Technical Committee Meeting on Response of Fuel, Fuel Elements and Gas Cooled Reactor Cores Under Accidental Air or Water Ingress Conditions, Beijing, China, Oct. 25–27) are presented and discussed.

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