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Htr 2014 Paper Comparison Of Fission Product Release Predictions Using Parfume With Results From The Agr 1 Safety Tests
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Book Synopsis HTR 2014 Paper - Comparison of Fission Product Release Predictions Using PARFUME with Results from the AGR-1 Safety Tests by :
Download or read book HTR 2014 Paper - Comparison of Fission Product Release Predictions Using PARFUME with Results from the AGR-1 Safety Tests written by and published by . This book was released on 2001 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Safety tests were conducted on fourteen fuel compacts from AGR-1, the first irradiation experiment of the Advanced Gas Reactor (AGR) Fuel Development and Qualification program, at temperatures ranging from 1600 to 1800°C to determine fission product release at temperatures that bound reactor accident conditions. The PARFUME (PARticle FUel ModEl) code was used to predict the release of fission products silver, cesium, strontium, and krypton from fuel compacts containing tristructural isotropic (TRISO) coated particles during the safety tests, and the predicted values were compared with experimental results. Preliminary comparisons between PARFUME predictions and post-irradiation examination (PIE) results of the safety tests show an overall over-prediction of the fractional release of these fission products, which is largely attributed to an over-estimation of the diffusivities used in the modeling of fission product transport in TRISO-coated particles. Correction factors to these diffusivities were assessed for silver and cesium in order to enable a better match between the modeling predictions and the safety testing results. In the case of strontium, correction factors could not be assessed because potential release during the safety tests could not be distinguished from matrix content released during irradiation. In the case of krypton, all the coating layers are partly retentive and the available data did not allow to determine their respective retention powers, hence preventing to derive any correction factors.
Book Synopsis HTR-2014 Paper Comparison of Fission Product Release Predictions Using PARFUME with Results from the AGR-1 Irradiation Experiment by :
Download or read book HTR-2014 Paper Comparison of Fission Product Release Predictions Using PARFUME with Results from the AGR-1 Irradiation Experiment written by and published by . This book was released on 2001 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The PARFUME (PARticle FUel ModEl) code was used to predict fission product release from tristructural isotropic (TRISO) coated fuel particles and compacts during the first irradiation experiment (AGR-1) of the Advanced Gas Reactor Fuel Development and Qualification program. The PARFUME model for the AGR-1 experiment used the fuel compact volume average temperature for each of the 620 days of irradiation to calculate the release of fission products silver, cesium, and strontium from a representative particle for a select number of AGR-1 compacts. Post-irradiation examination (PIE) measurements provided data on release of fission products from fuel compacts and fuel particles, and retention of fission products in the compacts outside of the SiC layer. PARFUME-predicted fractional release of these fission products was determined and compared to the PIE measurements. Results show an overall over-prediction of the fractional release of cesium by PARFUME. For particles with failed silicon carbide (SiC) layers, the over-prediction is by a factor of about two, corresponding to an over-estimation of the diffusivity in uranium oxycarbide (UCO) by a factor of about 100. For intact particles, whose release is much lower, the over-prediction is by an average of about an order of magnitude, which could additionally be attributed to an over-estimated diffusivity in SiC by about 30%. The release of strontium from intact particles is also over-estimated by PARFUME, which also points towards an over-estimated diffusivity of strontium in either SiC or UCO, or possibly both. The measured strontium fractional release from intact particles varied considerably from compact to compact, making it difficult to assess the effective over-estimation of the diffusivities. Furthermore, the release of strontium from particles with failed SiC is difficult to observe experimentally due to the release from intact particles, preventing any conclusions to be made on the accuracy or validity of the PARFUME predictions and the modeled diffusivity of strontium in UCO. In the case of silver, the comparisons between PARFUME and PIE are better than for cesium and strontium. They show a trend of over-prediction at low burnup and under-prediction at high burnup. PARFUME has limitations in the modeling of the temporal and spatial distributions of the temperature and burnup across the compacts, which affects the accuracy of its predictions. Nevertheless, the comparisons lie in the same order of magnitude.
Book Synopsis Comparison of Fission Product Release Predictions Using PARFUME with Results from the AGR-1 Safety Tests by :
Download or read book Comparison of Fission Product Release Predictions Using PARFUME with Results from the AGR-1 Safety Tests written by and published by . This book was released on 2014 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Comparison of Fission Product Release Predictions Using PARFUME with Results from the AGR-1 Irradiation Experiment by :
Download or read book Comparison of Fission Product Release Predictions Using PARFUME with Results from the AGR-1 Irradiation Experiment written by and published by . This book was released on 2014 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This report documents comparisons between post-irradiation examination measurements and model predictions of silver (Ag), cesium (Cs), and strontium (Sr) release from selected tristructural isotropic (TRISO) fuel particles and compacts during the first irradiation test of the Advanced Gas Reactor program that occurred from December 2006 to November 2009 in the Advanced Test Reactor (ATR) at Idaho National Laboratory (INL). The modeling was performed using the particle fuel model computer code PARFUME (PARticle FUel ModEl) developed at INL. PARFUME is an advanced gas-cooled reactor fuel performance modeling and analysis code (Miller 2009). It has been developed as an integrated mechanistic code that evaluates the thermal, mechanical, and physico-chemical behavior of fuel particles during irradiation to determine the failure probability of a population of fuel particles given the particle-to-particle statistical variations in physical dimensions and material properties that arise from the fuel fabrication process, accounting for all viable mechanisms that can lead to particle failure. The code also determines the diffusion of fission products from the fuel through the particle coating layers, and through the fuel matrix to the coolant boundary. The subsequent release of fission products is calculated at the compact level (release of fission products from the compact) but it can be assessed at the particle level by adjusting the diffusivity in the fuel matrix to very high values. Furthermore, the diffusivity of each layer can be individually set to a high value (typically 10-6 m2/s) to simulate a failed layer with no capability of fission product retention. In this study, the comparison to PIE focused on fission product release and because of the lack of failure in the irradiation, the probability of particle failure was not calculated. During the AGR-1 irradiation campaign, the fuel kernel produced and released fission products, which migrated through the successive layers of the TRISO-coated particle and potentially through the compact matrix. The release of these fission products was measured in PIE and modeled with PARFUME.
Book Synopsis A comparison of the fission product release predictions of MATREL and FASTGRASS during a severe reactor accident by : A. J. Manley
Download or read book A comparison of the fission product release predictions of MATREL and FASTGRASS during a severe reactor accident written by A. J. Manley and published by . This book was released on 1985 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Modeling of Fission Product Release from HTR (high Temperature Reactor) Fuel for Risk Analyses by :
Download or read book Modeling of Fission Product Release from HTR (high Temperature Reactor) Fuel for Risk Analyses written by and published by . This book was released on 1989 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The US and FRG have developed methodologies to determine the performance of and fission product release from TRISO-coated fuel particles under postulated accident conditions. The paper presents a qualitative and quantitative comparison of US and FRG models. The models are those used by General Atomics (GA) and by the German Nuclear Research Center at Juelich (KFA/ISF). A benchmark calculation was performed for fuel temperatures predicted for the US Department of Energy sponsored Modular High Temperature Gas Cooled Reactor (MHTGR). Good agreement in the benchmark calculations supports the on-going efforts to verify and validate the independently developed codes of GA and KFA/ISF. This work was performed under the US/FRG Umbrella Agreement for Cooperation on Gas Cooled Reactor Development. 6 refs., 3 figs., 3 tabs.
Book Synopsis Kinetics of Fission Product Release Prior to Fuel Slumping by :
Download or read book Kinetics of Fission Product Release Prior to Fuel Slumping written by and published by . This book was released on 1987 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This paper describes the primary physical/chemical models recently incorporated into a mechanistic code (FASTGRASS) for the estimation of fission product release from fuel, and compares predicted results with test data. The theory of noble gas behavior is discussed in relation to its effect on the release behavior of I, Cs, Te, Ba, and Sr. The behavior of these fission products in the presence of fuel liquefaction/dissolution and oxidation grain-growth phenomena is presented, as is the chemistry of Sr, Ba, I, and Cs. Comparison of code predictions with data indicates the following trends. Fission product release behavior from solid strongly depends on fuel microstructure, irradiation history, time at temperature, and internal fuel rod chemistry. Fuel liquefaction/dissolution, fracturing, and oxidation also exert a pronounced effect on release during fuel rod degradation. For very low burnup fuel appreciable fission product retention in previously liquefied fuel can occur due to the low concentration of fission products, and the limited growth of bubbles in the liquefied material. 24 refs., 13 figs., 9 tabs.
Book Synopsis Data Summary Report for Fission Product Release Test VI-1 by :
Download or read book Data Summary Report for Fission Product Release Test VI-1 written by and published by . This book was released on 1989 with total page 59 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Assessment of Improved Fission-product Transport Models in VICTORIA Against the ORNL HI and VI Tests by :
Download or read book Assessment of Improved Fission-product Transport Models in VICTORIA Against the ORNL HI and VI Tests written by and published by . This book was released on 1991 with total page 23 pages. Available in PDF, EPUB and Kindle. Book excerpt: New models for the release of fission-products from fuel have recently been incorporated into a comprehensive code, VICTORIA, for the prediction of radionuclide behavior under severe reactor accident conditions as an alternative to a simple Booth diffusion calculation. It is widely known that the Booth model has severe limitations when used under conditions of changing temperature and power. A new transport model based on a two node diffusive flow formulation has been implemented into VICTORIA. In addition to the diffusive flow model, other mechanisms such as grain growth, grain boundary sweeping and intergranular bubble behavior are taken into account. These physically based models focus on fission-product behavior in intact fuel geometries. While the VICTORIA program is primarily concerned with the behavior of severely degraded fuel geometries, the capability for accurately characterizing fission-product release from intact fuel must be demonstrated before other geometries can be reliably modeled. Results of VICTORIA simulations are compared with the results of in-cell heating tests on irradiated fuel. The fission-product transport models involved in these simulations are assessed and their predictive capability examined. 10 refs., 7 figs., 2 tabs.
Book Synopsis Comparison of fission gas release data with Supatrice 2 predictions at S.G.H.W.R. fuel ratings by : C. B. Cowking
Download or read book Comparison of fission gas release data with Supatrice 2 predictions at S.G.H.W.R. fuel ratings written by C. B. Cowking and published by . This book was released on 1968 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Data Summary Report for Fission Product Release Test HI-5 by :
Download or read book Data Summary Report for Fission Product Release Test HI-5 written by and published by . This book was released on 1985 with total page 61 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis A review of volatility data for selected fission product elements by : W. G. Burns
Download or read book A review of volatility data for selected fission product elements written by W. G. Burns and published by . This book was released on 1990 with total page 23 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Fission Product Behavior During the PBF Severe Fuel Damage Test 1-1 by : Jack K. Hartwell
Download or read book Fission Product Behavior During the PBF Severe Fuel Damage Test 1-1 written by Jack K. Hartwell and published by . This book was released on 1987 with total page 172 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Fission Product Release written by and published by . This book was released on 1996 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Fission Product Transport Analysis by : James A. Gieseke
Download or read book Fission Product Transport Analysis written by James A. Gieseke and published by . This book was released on 1976 with total page 8 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis A review of international data on fission-product release under reactor accident conditions by : P. H. Elder
Download or read book A review of international data on fission-product release under reactor accident conditions written by P. H. Elder and published by . This book was released on 1997 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Data Summary Report for Fission Product Release Test HI-3 by : M. F. Osborne
Download or read book Data Summary Report for Fission Product Release Test HI-3 written by M. F. Osborne and published by . This book was released on 1984 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
