Nuclear Technology ISSN: 0029-5450 (Print) 1943-7471 (Online) Journal homepage: www.tandfonline.com/journals/unct20 Behavior of a UF6 Container during a Fire&I: Analysis and Phenomenological Interpretation of Tenerife Experimental Results Eric Pinton, Bernard Duret & Georges Berthoud To cite this article: Eric Pinton, Bernard Duret & Georges Berthoud (1999) Behavior of a UF6 Container during a Fire&I: Analysis and Phenomenological Interpretation of Tenerife Experimental Results, Nuclear Technology, 127:3, 332-351, DOI: 10.13182/NT99-A3005 To link to this article: https://doi.org/10.13182/NT99-A3005 Published online: 10 May 2017. Submit your article to this journal Article views: 6 View related articles Full Terms & Conditions of access and use can be found at https://www.tandfonline.com/action/journalInformation?journalCode=unct20 BEHAVIOR OF A UF6 CONTAINER DURING A FIRE—I: ANALYSIS AND PHENOMENOLOGICAL INTERPRETATION OF TENERIFE EXPERIMENTAL RESULTS THERMAL HYDRAULICS KEYWORDS: safety of nuclear fuel transport, nuclear safety, thermal hydraulics ERIC PINTON,* BERNARD DURET, and GEORGES BERTHOUD† Commissariat à l’Energie Atomique, Direction des Réacteurs Nucléaires Grenoble, France Received December 30, 1997 Accepted for Publication March 3, 1999 I. PRESENTATION OF THE PROBLEM To improve the knowledge of the behavior of a UF6 container during a fire, an experimental project called Tenerife was conducted by the Commissariat à l’Energie Atomique. Three tests with UF6 with different kinds of heating and temperature furnaces were carried out. The main information obtained from monitoring temperature and pressure during the heating tests is as follows: 1. The presence of a strong thermal contact resistance at the solid UF6-steel interface. 2. The rupture of the solid crust at the top of the container, a crust formed during container cooling after filling, for a pressure reaching 1.5 bars (triple point). This leads to the beginning of boiling heat transfer and notably film boiling, followed by transition boiling and nucleate boiling. 3. The appearance of the liquid stratification with the beginning of nucleate boiling. It can accelerate the rise in pressure because of the reduction of mass transfer by condensation to the liquid-gas interface. This stratification is preserved with the natural convection regime that replaces the nucleate boiling after the end of heating. 4. After rupture of the upper UF6 crust, the pressure increase may be delayed by different wetting of the UF6 on the steel wall. Also, these tests were allowed to build and validate a scenario that has been reproduced in a numerical model. *Current address: Robatel, rue de genève, BP 203, 69741 Genas Cedex, France. †E-mail: georges.berthoud@cea.fr 332 I.A. Introduction Uranium hexafluoride is the raw material from which the fuel for nuclear power plants is obtained. It is stored and transported in the solid state in steel industrial containers similar to the one shown in Fig. 1. The International Atomic Energy Agency ~IAEA! envisages a revision of current regulations and suggests that a container should withstand a specific fire test 1 ~engulfing fuel fire of 8008C for 0.5 h, for a steel emissivity of 0.8 and flame emissivity of 0.9!. To study the safety of the containers under these conditions a numerical model was created by the Commissariat à l’Energie Atomique ~CEA!. A two-dimensional model that uses the finite element computation code ANSYS was developed. It takes into account thermal and mechanical phenomena as well as mass transfer.2 Modeling and validation are presented in Part II of this paper.3 This model must be validated with reliable and representative experimental results. Over the past 30 yr, a number of experiments on UF6 containers under fire conditions have been performed. The best instrumented and the most interesting was conducted by Suzuki et al.4 However, they do not in any way reflect realistic conditions. The dimensions of the test containers were much smaller than those of a 48Y container ~107 kg instead of 12 500!, and the simulated fire temperatures were too low ~4008C instead of 800!. Although it is possible to estimate the thermohydraulic behavior of the UF6 from these tests, many uncertainties remain ~rupture of the UF6 top crust and its influence on transfer, liquid emergence, boiling type at the steelliquid UF6 interface, value of the thermal contact resistance steel-UF6 solid, pressure evolution, mass transfer, etc.!. A numerical model can only be partially validated with these results. Therefore, it was necessary for us to NUCLEAR TECHNOLOGY VOL. 127 SEP. 1999 Pinton et al. URANIUM HEXAFLUORIDE BEHAVIOR IN FIRE Fig. 1. Schema and description of 48Y container. conduct tests where the experimental container shape and the fire simulation are close to the real conditions. Consequently, an experimental project called Tenerife 5 was defined and conducted in the scope of a joint research program between France ~CEA! and Japan ~Central Research Institute of the Electric Power Industry!. The experimental side of this project is carried out by the Institute for Protection and Nuclear Safety in the facility for research on fires at the CEA Cadarache ~France! Research Centre. The fire is simulated with an electric furnace consisting of radiant INCONEL a panels capable of reaching a temperature up to 10008C in 4 min. The Tenerife container is identical to a 48Y container except that its length is reduced by one third to limit the amount of UF6 ~4 tonnes instead of 12.5! and also to limit the overall dimensions of the furnace ~see Fig. 2!. This paper presents the phenomenological interpretation and the lessons a INCONEL is a trademark of the Inco family of companies. NUCLEAR TECHNOLOGY VOL. 127 SEP. 1999 learned from these tests carried out with different furnace temperatures and heating time.5 I.B. Different Rupture Modes and Description of the UF6 Uranium hexafluoride, the only material inside the container, is a solid at ambient temperature in equilibrium. When heated, the vapor sublimates without melting, as shown in the phase diagram ~Fig. 3!, which also shows that 1. The solid-liquid phase change appears at the triple point ~648C, 1.52 3 10 5 Pa!. 2. The UF6 melts at a constant temperature of 648C. 3. For a pressure above that of the triple point, the three phases coexist. 4. The vapor pressure rises steeply with the liquid temperature to reach the critical point at a value of 46 bars with a corresponding temperature of 2308C. 333 Pinton et al. URANIUM HEXAFLUORIDE BEHAVIOR IN FIRE Fig. 2. Schema and description of Tenerife container with the furnace. Increase of the internal pressure with the rise of UF6 temperature coupled with the decrease of the steel mechanical properties at high temperature @see Fig. 16 of Part II ~Ref. 3!# can lead to rupture of the metal casing. The container-filling regulation involves a gaseous cavity at the top of the container of about one-third of the inner volume. Thus, during the heating, melting of UF6 entails a significant decrease in density Dr0rS 5 25% ~Fig. 4!, and thus, the liquid level will increase progressively with time until it eventually occupies all of the inner volume. There is then a risk that the container will tear open under the force of hydraulic pressure. The overall physical properties can be found in the compilations of De Witt 6 and Anderson et al.,7 which assemble and examine practically all the literature published on the properties of UF6 . I.C. Initial State of the UF6 and Cooling of the Container After Filling Fig. 3. Phase diagram for UF6 . 334 The initial structure of the solid UF6 within the container is still not well known, since it is very difficult to see inside the 48Y. However, it can be estimated by analyzing the cooling process of UF6 after filling by taking internal temperature measurements during cooling of a Tenerife container. The quantity of UF6 input in the liquid NUCLEAR TECHNOLOGY VOL. 127 SEP. 1999 Pinton et al. URANIUM HEXAFLUORIDE BEHAVIOR IN FIRE Fig. 5. Cooling of UF6 after filling. Fig. 4. Density of UF6 . state at 808C complies with the regulation that only 95% of the volume must be occupied by the UF6 at 1208C. The measurements indicate that the temperature of the liquid UF6 becomes rapidly uniform at 648C, and then the gas occupies ;15% of the inner volume as shown on Fig. 5. Subsequently, the UF6 solidifies on the cold wall of the steel cylinder. As the density of the liquid is less than the solid, the liquid level is reduced. Crystallization of UF6 gas at the top of the container forms a solid crust. This one has been observed during an endoscopic visualization attempt. In the region not close to the wall, which we call the “core,” the crystallization seems different. Indeed, measurements reveal a thermal gradient in the solid in the vicinity of the steel, while in the core, temperatures remain homogeneous at 648C until all the liquid disappears. Then, temperatures fall together. This type of solidification is comparable to solidification of metal castings: Externally there is nucleation at the wall; from these points a dendrite grows, following the thermal gradient; and bulk freezing of the liquid occurs in an equiaxed configuration. These two types of crystallization entail equally a difference of porosity. The UF6 depositing gradually along the wall is very compact and has a normal density of ;5000 kg0m 3. On the other hand, in the solid core, inner voids appear. These are estimated at ;25%, which corresponds to the difference between the liquid and solid densities. NUCLEAR TECHNOLOGY VOL. 127 SEP. 1999 The thickness of the solid crust at the top of the container and that of the solid next to the wall depend on the external cooling conditions. Moreover, conditions of storage ~sunniness, external temperature, etc., leading to inner mass transfer! can also influence the initial configuration of the UF6 . Therefore, the initial UF6 configuration will not be identical for all containers and will depend on their history. II. INTERPRETATION OF THE TEN2 TEST II.A. Introduction Two tests were carried out on the container called TEN2, enclosed in the furnace at 8008C: the first with a 10-min heating ~June 29, 1995! and the second with an 18-min heating ~July 6, 1995!. Since the 18-min test provides most of the information, the analysis of the 10-min test will not be presented in this paper. The steel temperature evolution, then that of UF6 , and finally the pressure evolution will be discussed. On the figures presented in this paper, time t 5 0 corresponds to the heating initiation. The instrumentation consists of the following: 1. 2 pressure sensors P1 and P2 2. 16 thermocouples ~T1 to T16! in three tubes inside the container 335 Pinton et al. URANIUM HEXAFLUORIDE BEHAVIOR IN FIRE Fig. 6. Instrumentation of the TEN2 container. 3. 8 thermocouples ~TP1 to TP8! on two combs near the inner wall 4. 15 thermocouples ~A1 to A15! on the inner surface of the container 5. 10 thermocouples ~TJ1 to TJ10! and 10 strain gauges ~J1 to J10! on the outer surface of the container. Details on the positions of these measurement points can be found in Fig. 6. On some of the figures, the saturation temperature is shown, calculated from the pressure measured by sensor P1 ~range 0 to 7 bars! or P2 ~range 0 to 20 bars!. Fig. 7. Definition of the median plane and the steel internal thermocouples in this plane. II.B. Interpretation of the Steel Temperatures II.B.1. The Steel Inner Temperatures in the Median Plane The median plane is the plane running through the middle of the container as shown in Fig. 7. The temperatures in the median plane are discussed as follows: 1. 0 , t , 250 s: The steel receives the radiant energy from the furnace, and its temperature rises progressively. At time 165 s, all the steel temperatures reach a 336 plateau that lasts for ;20 s, and then they continue to rise until 230 s, where the same phenomena seem to occur. We explain these two phenomena by increased heat transfer between steel and UF6 . Indeed, these two phenomena are accompanied by a significant increase in pressure @see Tsat ~P1! on Fig. 8#, so it seems that a crack occurs in the crust, leading to an infiltration of the gas contained between the steel and the solid UF6 @which is at a higher pressure than the gas blanket Psat ~TUF6 ! . P1# toward the gas volume, as shown in Fig. 9. This NUCLEAR TECHNOLOGY VOL. 127 SEP. 1999 Pinton et al. URANIUM HEXAFLUORIDE BEHAVIOR IN FIRE Fig. 8. Evolution of the steel inner temperatures in the median plane from 0 to 250 s. Fig. 9. Interpretation of the temperature plateau. contributed to increasing the pressure and to improving exchanges at the steel inner surface. As soon as the crack is sealed by condensation of the vapor, the steel resumes its normal temperature evolution. The thermocouples measuring the inner temperatures of the metal wall are simply kept in contact ~Fig. 10! by a spot-welded steel sheet. The strange temperature decrease, corresponding to the second phenomenon, surely results from significant arrival of UF6 cold gas on the thermocouples. 2. 350 , t , 540 s: The temperature continues to rise, as shown in Fig. 11. At time t 5 420 s, all the tem- Fig. 10. Location of the internal steel thermocouples. NUCLEAR TECHNOLOGY VOL. 127 SEP. 1999 peratures are .2008C, even while the inside UF6 is still in solid state. Now, in the case of perfect contact, the metal temperature should not exceed the UF6 melting temperature because the UF6 is still solid ~if it was liquid, wetting of the wall would have entailed a change of slope!. This confirms the existence of a significant contact resistance also present at the level of the crust on the top of the container. At time 440 s, it seems that liquid appears almost simultaneously at the levels of A14, A13, and A15. There is in fact a slight change of slope in the steel temperature curve, indicating improved heat exchange. Even in the presence of the liquid, exchange is limited by the depth and conductivity of the liquid UF6 . Therefore, the steel temperature continues to increase steadily. However, this temperature is higher than the critical temperature ~2308C!, indicating the presence of a supercritical fluid next to the metal wall. Nevertheless, it must stay liquid in the vicinity of the solid UF6 interface, which is at 648C. Actually, the UF6 fluid ~whose state is not well known! is confined between the wall and the solid UF6 . Referring to Fig. 11, the contact resistance would seem to be greater in the lower part of the container than in the upper part since A14, A13, and A15 are greater than A9, A10, A11, and A12. If this were the case, the UF6 in the upper part would receive more energy, and the liquid should therefore appear first in this zone. However, it seems first to appear at the bottom, which is an apparent contradiction. In our opinion, it is rather that the lower part of the steel container receives more energy than the part near the top. This is confirmed by the fact that temperatures of the INCONEL furnace for positions facing the steel are found to be higher in the bottom zone. 337 Pinton et al. URANIUM HEXAFLUORIDE BEHAVIOR IN FIRE Fig. 11. Evolution of the steel inner temperatures in the median plane from 350 to 540 s. 3. 540 , t , 800 s: At 540 s the upper crust collapses as will be demonstrated later ~in Sec. II.C.1 from 540 to 650 s and in Sec. II.C.2 at 540 s!. Thus, the pressurized interstitial liquid is back at the pressure of the cavity and starts to boil. Single-phase exchange is replaced by film boiling because of important superheat between wall and saturation temperature Tp 2 Tsat . 2008C. Heat transfer at the wall improves and leads to a change of the slope of the measurements at A13, A14, and A15, as shown on Fig. 12. The liquid level gradually rises and seems to reach A11 at 600 s and then A9 at 720 s ~change in slope!. There is then an acceleration in the fall of the steel temperatures. This is characteristic of the switch from film boiling to nucleate boiling that goes through a transition boiling phase where the flux exchanged at the wall qBoil increases with the decrease in wall temperature Tw , as shown on Fig. 13. In nucleate boiling, heat exchange is excellent so that the flux exchanged on the boiling surface qBoil rapidly balances the external flux qext , which in our case is the radiant flux from the furnace. As this flux is practically constant over the whole surface, the temperatures of the steel in contact with the liquid do not change anymore, as shown on Fig. 12 ~at t 5 800 s!. 4. 800 , t , 1080 s: Over this period, the steel temperature is practically Tsat and follows the evolution of Fig. 12. Evolution of steel inner temperatures in the median plane from 500 to 1500 s. 338 NUCLEAR TECHNOLOGY VOL. 127 SEP. 1999 Pinton et al. URANIUM HEXAFLUORIDE BEHAVIOR IN FIRE Fig. 13. General characteristic curve of boiling heat exchanges. Tsat . The reason needs explanation. During boiling, the flux is governed essentially by the superheat Tw 2 Tsat . The external flux is nearly constant; thus to conserve flux balance qBoil 5 qext , the superheat must be kept constant. The wall temperature Tw therefore follows the evolution of saturation temperature Tsat . In nucleate boiling, the exchange coefficient is also very high, so a small superheat is sufficient to transmit a high flux. This explains why Tw ' Tsat . However, in the bottom zone, the wall temperature is below saturation temperature—a phenomenon that could be attributed to the presence of natural convection with no boiling. In fact, the internal thermocouples are laid on the metal surface so that they are in contact with both the steel and the UF6 ~liquid or solid!, as shown on Fig. 10. Thus, we believe that the value measured at the end of the thermocouples is some mean value of the steel and UF6 temperatures. Depending on the exchange between the thermocouple sheath and the UF6 , the measured value may underestimate the true inner temperature of the steel. 5. Particular Case of A9 and A10 (Near the Liquid Level): During transition boiling, the major part of the flux is used to produce vapor. When nucleate boiling is established, the vapor output decreases rapidly. There is a reduction in the volume occupied by the bubbles causing a drop in the liquid level, as shown on Fig. 14. We consider that at time t 5 780 s, A9 is no longer in contact with the liquid, and since there is less exchange with the gas, the temperature of A9 increases slightly ~until 850 s!. However, since A9 is close to the interface, it falls within the lateral thermal gradient, as illustrated on Fig. 15. As heat exchanges continue, the UF6 level rises with solid melting. The steel thermal gradient moves upward, leading to a decrease in the temperature of A9 ~from 850 to 1080 s!. 6. t . 1080 s: The radiant energy coming from the INCONEL and received by the steel gradually decreases, leading to a drop in the steel temperature. The boiling regime then switches from nucleate boiling to natural convection. The decrease in temperature begins first at the NUCLEAR TECHNOLOGY VOL. 127 SEP. 1999 Fig. 14. Variation in liquid level versus type of boiling. Fig. 15. Tangential thermal gradient in the steel near 800 s. bottom of the container and then propagates upward, indicating that natural convection starts at the bottom because the proximity of the solid improves the exchange and develops gradually upward to the top of the cylinder. When heating is stopped, the temperature values of A9 and A10 follow that of Tsat , indicating that the regime here is nucleate boiling. Lower down, at the level of thermocouples A13, A14, A15, A11, and A12, the regime is natural convection. Boiling near the liquid level is due to the thermal energy stored in the upper zone of the container that continues to stream down to the lower zone by conduction ~see Fig. 15!. This conductive flux ~along with exchanges with the furnace due to its thermal inertia! is therefore sufficient to maintain nucleate boiling close to the liquid-gas interface. Figure 16 shows that the temperature of A8 ~top of the container! increases almost linearly from 540 to 1080 s, i.e., from the time the crust collapses until heating is stopped. The radiant flux received on the outer surface of the steel is therefore still higher than that of the 339 Pinton et al. URANIUM HEXAFLUORIDE BEHAVIOR IN FIRE Fig. 16. Temperature evolution of A8 and of the INCONEL opposite A8. radiant and convective flux exchanged on the inner surface. When the heating is stopped, the temperature of A8 gradually decreases, and eventually it becomes higher than that of the INCONEL. From then on ~1500 s!, the steel is no longer receiving energy from the furnace but, on the contrary, transfers energy to the INCONEL. II.B.2. The Steel Temperatures in the Horizontal Axial Plane The horizontal axial plane is the plane through the middle of its axis, as illustrated in Fig. 17. The evolution of A5, A6 and A11, A12 is practically identical ~see Fig. 18!. On the whole, edge effects are practically nonexistent on the cylindrical part. The temperature rise of TJ1 falls off at ;180 s, which suggests that contact is improved. The liquid appears at ;500 s ~change of the slope!. Thus, TJ2 remains low be- cause it receives less energy due to its location ~see Fig. 6!. II.C. Interpretation of the UF6 Temperatures In what follows, we will begin by interpreting the evolution of UF6 temperatures in the upper part of the median plane ~T2, T3, T4, T5, T6, and T7!, then in the lower part ~T8, T9, T10, T12, T13, T15, and T16!, and conclude by the interpretation of the temperatures corresponding to comb 2 ~TP5, TP6, TP7, and TP8!. Thermocouple locations are given in Fig. 6. II.C.1. The UF6 Temperatures on the Upper Part of the Median Plane The UF6 temperatures on the upper part of the median plane are as follows ~see Fig. 19!: Fig. 17. Definition of the horizontal axial plane and the thermocouples positioned in this plane. 340 NUCLEAR TECHNOLOGY VOL. 127 SEP. 1999 Pinton et al. URANIUM HEXAFLUORIDE BEHAVIOR IN FIRE Fig. 18. Evolution of steel temperatures in the horizontal axial plane. Fig. 19. Temperature evolution in the upper part of the median plane from 0 to 800 s. 1. t 5 0 s: The saturation temperature Tsat should be that of the initial temperature of the system Tini , i.e., ;368C in this test. However, Tsat ~P1! , Tini , which means that the value measured by sensor P1 slightly underestimates the pressure, possibly because of calibration errors. 4. 180 , t , 240 s: T2, T3, T4, and T44 increase with Tsat ~P !, whereas the other thermocouple values remain unchanged, except for T7, which rises very slightly. 2. t , 180 s: T3 and T2 evolve with Tsat ; this means that T2 and perhaps T3 are in the gas phase. The other temperatures do not change. 6. 240 , t , 540 s: All the thermocouples in the upper part follow Tsat ~P !. 3. t 5 180 s: There is a sudden rise in temperatures of T2, T3, T4, and T44, which increase with Tsat ~P!. NUCLEAR TECHNOLOGY VOL. 127 SEP. 1999 5. t 5 240 s: The readings of T5, T6, and T7 rise suddenly to the temperature of Tsat ~P !. 7. t 5 540 s: All the UF6 in the upper part reaches the triple point temperature, i.e., 648C, where the liquid phase can begin to exist. 341 Pinton et al. URANIUM HEXAFLUORIDE BEHAVIOR IN FIRE 12. t 5 780 s: The UF6 at the levels of T5 and T6 becomes liquid. Fig. 20. Evolution of the Tsat ~P ! front in the solid UF6 . 8. Analysis: Thermocouples T3 and T2 seem to be in the UF6 gas and the other thermocouples in solid UF6 . There seems to be a gradual diffusion of heat from the solid-gas horizontal interface toward the bottom of the solid and a Tsat ~P ! front that propagates as shown on Fig. 20. In the inner part of the front where the temperatures are at Tsat ~P !, the heat exchanges are excellent since the temperatures evolve in a uniform manner. The heat input would be due in particular to the condensation of the vapor ~cold surface! that sublimated at the solid-gas interface of the crust ~hot surface!. 9. 540 , t , 650 s: At ;540 s, T2 temperature increases suddenly and becomes significantly higher than Tsat ~P !. This seems to be the moment the top crust collapses allowing the gas to come into contact with the “superheated” steel and to rise in temperature. At 590 s, liquid UF6 running along the thermocouple encounters the weld and causes a drop in temperature. Thermocouple T3 increases with Tsat ~P !; it must be near the liquid-gas interface. The other temperatures remain unchanged ~648C! at the solid-liquid equilibrium temperature. 10. t 5 650 s: There is a change of phase at T4 and T7 from the solid to the liquid phase because their temperatures, constant up to now, begin to rise. 11. 650 , t , 780 s: From 700 s, T2 temperature decreases due to the switch from film boiling to nucleate boiling. In fact, the flux exchanged on the boiling surface and the generation of vapor increase considerably during the transition. In addition, with the reduction in wall temperature and the change in the type of transfer between liquid and steel, the vapor is less and less superheated and reaches saturation under nucleate boiling conditions. A large quantity of cold vapor arrives and then mixes with the gas blanket and causes its temperature to drop. Thermocouples T4, T7, and T3 are approximately at the saturation temperature of Tsat ~P !. We can consider that the motion in the liquid at the top, caused by the generation of a large amount of vapor ~under film boiling and then transition boiling conditions!, tends to equalize the temperature of the liquid. 342 13. 780 , t , 870 s: Thermocouple T3 still evolves with Tsat ~P !. The liquid level seems to remain constant. Temperatures of T5 and T6 rise rapidly to that of T7. The motion in the upper liquid remains important although its equalizing effect is not so obvious. On approaching equilibrium between the external flux and the nucleate boiling flux, the generation of vapor is considerably reduced. The energy absorbed by the gas, by absorption in infrared radiation and by convection with the steel, becomes higher than that added by the cold vapor released by boiling. The temperature of vapor located in the gas pocket rises as indicated by T2. 14. 870 , t , 1080 s: At 880 s, the motion in the liquid appears to cease and give way to a thermal stratification. In fact, the temperature of the liquid now decreases regularly from the liquid-gas horizontal interface at Tsat to the solid-liquid interface at 648C ~Fig. 21!. We see that the liquid temperatures in the same horizontal plane ~T5, T6, and T7! are identical. This phenomenon is explained in Sec. II.C.3. At 1020 s, T3 , Tsat ~P !, the free surface of the liquid pool becomes above the position of T3 @if Tinterface 5 Tsat ~P1!#. 15. t . 1080 s: There is a gradual change from nucleate boiling to natural convection along the steel wall. Gradually, the free surface of UF6 decreases, which is shown on the thermocouples that reach the saturation temperature as seen on Fig. 22 ~temperature of the liquidgas interface!. However, that evolution has a time delay, as is clearly evident from the maximum measurements ~T3 and then T4, T6, etc.!. The closer to the interface, the shorter the time delay and the stronger the influence of the interface. II.C.2. UF6 Temperatures in the Lower Part of the Median Plane The UF6 temperatures in the lower part of the median plane are as follows ~see Fig. 23!: 1. 0 , t , 540 s: As in the upper part, sudden changes of temperature occur from the top to the bottom until they reach Tsat ~P !. The phenomenon found for the UF6 in the upper part seems to prevail right down to the bottom of the container. We explain this by a sudden mass transfer of UF6 vapor coming from the gaseous cavity through porosities of solid UF6 in a preferential manner along the tube supporting the thermocouples. The liquid appears first at T11 ~370 s! and then at T16 ~430 s!. This may also be explained by the fact that the INCONEL temperature, and therefore the energy received by the steel, is higher at T11 ~Tinco : 8308C! than at T16 ~Tinco : 8058C!. NUCLEAR TECHNOLOGY VOL. 127 SEP. 1999 Pinton et al. URANIUM HEXAFLUORIDE BEHAVIOR IN FIRE Fig. 21. Evolution of UF6 temperatures in the upper part of the median plane from 500 to 1100 s. Fig. 22. Evolution of UF6 temperatures in the upper part of the median plane from 0 to 180 000 s. 2. t 5 540 s: At this time the collapse of the crust is assumed to take place, with the result that the liquid confined between the solid and the steel is exposed to the gas blanket. As this liquid is superheated @compared to Tsat ~P !# , especially at the level of T11 and T16, there will be sudden evaporation with cooling of the liquid until equilibrium is reached, i.e., until Tliq ' Tsat ~P !. 3. 540 , t , 760 s: In the neighborhood of 540 s, practically all the thermocouples are at UF6 melting temperature and therefore all at solid-liquid equilibrium, NUCLEAR TECHNOLOGY VOL. 127 SEP. 1999 which is not compatible with an energy balance.2 In fact, the radiant heat flux received by the steel surface and heat transfer at the steel-solid UF6 interface ~thermal contact resistance! are relatively well known. In this case, energy transmitted to UF6 can be evaluated. The global temperature of the solid mass at 540 s, given by the computation, would be of 428C, i.e., 68C above the initial temperature, instead of the 288C observed in the experiment. At t 5 680 s, all the thermocouples located in the bottom part seem to be in the liquid phase, except for T9, which remains in the solid. 343 Pinton et al. URANIUM HEXAFLUORIDE BEHAVIOR IN FIRE Fig. 23. Evolution of UF6 temperatures in the lower part of the median plane from 100 to 1400 s. 4. 760 , t , 1400 s: Near 760 s, the superheated liquid undergoes a sudden temperature drop. Paradoxically, this drop occurs despite the fact that the flux at the wall is still significant ~see the strong drop of the steel temperatures in contact with the liquid in Fig. 12!, which is not logical. We believe that the solid, which up to this time had been attached to the tubes supporting the thermocouples, now sinks to the bottom of the container ~Fig. 24!. Other evidence supports this hypothesis, for example, the temperature at TP8 that increases suddenly ~Fig. 25!, which suggests that TP8 initially in the solid is now in the liquid bath ~see Fig. 24!. With the fall of the solid UF6 block, the temperature of the thermocouples decreases but nevertheless remains higher than 648C ~Tmelt !, as though some liquid remained. It can be assumed that liquid remains entrapped in the tubes and that it is surrounded by solid UF 6 , as illustrated on Fig. 24. This assumption will be confirmed in the next time period. Thermal equilibrium is then gradually attained. All the lower thermocouples have a uniform temperature that decreases gradually to stabilize at ;5 3 10 4 s, as illustrated on Fig. 26. Looking at the values of these thermocouples, the UF6 appears to be liquid. However, if this were the case, stratification between different locations of UF6 thermocouples should occur as in the upper part of the container. Moreover, there would be no reason for the temperature of T8 to rise above Tmelt . Thermocouple T8, in fact, breaks away at ;25 000 s because the solid around it has disappeared. Once freed from its solid prison, the thermocouple recovers the stratified medium of the liquid ~Fig. 27!. Moreover, an energy balance confirms that the UF6 can be entirely in the liquid state. Everything seems to indicate that the medium is liquid inside the tubes but solid outside the tubes. From T8 behavior, we conclude that there is still solid UF6 at the bottom of the container ~after 7 h the solid is 30 cm in height!. II.C.3. The Temperatures on Comb 2 (Near the Wall) The UF6 temperatures on comb 2 ~near the wall! are as follows: 1. 0 , t , 400 s: The nearer to the wall, the higher the temperature of the solid UF6 . This seems to indicate that at the combs, the energy received by the UF6 comes essentially from the steel. Fig. 24. Sinking of the solid. 344 2. t 5 400 s: Thermocouples TP5, TP6, and TP7 are at the same temperature. Only TP8 indicates a lower temperature. NUCLEAR TECHNOLOGY VOL. 127 SEP. 1999 Pinton et al. URANIUM HEXAFLUORIDE BEHAVIOR IN FIRE Fig. 25. Evolution of UF6 temperatures on comb 2 from 0 to 1100 s. Fig. 26. Evolution of UF6 temperatures in the lower part of the median plane from 0 to 5 3 10 5 s. 3. 400 , t , 540 s: The temperature of TP5 breaks away at 450 s and seems to reflect a liquid phase. With melting of the crust ~at ;540 s!, a high evaporation is observed that entails cooling of the liquid, as noted earlier. Thermocouples TP6 and TP7 evolve with Tsat ~P ! and TP8 continues to rise steadily. Fig. 27. Freeing of T8 from its solid prison. NUCLEAR TECHNOLOGY VOL. 127 SEP. 1999 4. 540 , t , 800 s: Thermocouples TP5, TP6, and TP7 are in the liquid phase since their temperatures are higher than melting temperature. They follow with Tsat ~P ! : The liquid seems to be in equilibrium with the vapor. This indicates significant agitation enabling the liquid temperature to remain uniform. 345 Pinton et al. URANIUM HEXAFLUORIDE BEHAVIOR IN FIRE least at Tsat ! and the first thermocouple 1 cm away from the wall ~Fig. 25!. In contrast, between 1 and 5 cm from the wall, the temperature is practically uniform. This confirms the assumption that the major input of energy from the wall is taken up by the bubbly boundary layer ~on a thickness lower than 1 cm at the level of the comb!. The energy contained in this layer is carried directly toward the liquid-gas interface. The convective motion results in an arrival of hot UF6 that will then initiate the stratification of the liquid in the upper part of the container ~see Fig. 28!. II.D. Interpretation of the Pressure Evolution 5. 800 , t , 880 s: Nucleate boiling occurs gradually, and the generation of vapor is smaller. The liquid agitation is less important, and a boundary layer bubble regime is installed. This less dynamic boundary layer transmits little energy to the liquid bath, leading to a temperature decrease. We have two pressure sensors available, one with a pressure range up to a maximum of 7 bars ~P1! and the other up to 20 bars ~P2!. The supplier of these sensors ensures that linearity is preserved to within 0.2% up to 150% of the full scale. Measurements are therefore usable up to 10.5 bars for P1 and 30 bars for P2. Note that on Fig. 29, the sensor P2 gives a pressure always higher than P1. Moreover, the difference between these two values increases with the pressure rise. It is logical to think that at a low pressure, P1 gives a better measurement than P2 because its range is limited to 7 bars, so it is more accurate. An extrapolation of P1 with respect to P2 would give a pressure at 1800 s of 25 bars instead of 29 bars as indicated by P2, so a reduction of ;4 bars may be closer to the correct value. The pressure evolution is as follows: 6. 880 , t , 1080 s: The wall temperature at comb level increases ~see A12 on Fig. 12!. There is a considerable temperature difference between the wall ~that is at 1. 0 , t , 180 s: The pressure slightly increases. Sublimation occurs at the hot interface of the crust and condensation on the colder solid interface at the bottom, Fig. 28. Boundary layer and liquid agitation. At t 5 760 s, TP8 ~5 cm from the wall! is in the liquid phase, and its temperature rises suddenly. It almost instantaneously stabilizes at Tsat ~P !, indicating very high heat transfer. Fig. 29. Pressure evolution from 0 to 1800 s. 346 NUCLEAR TECHNOLOGY VOL. 127 SEP. 1999 Pinton et al. to preserve thermodynamic equilibrium @the temperature of the solid-gas interface must be equal to Tsat ~P ! over its whole surface#. 2. t 5 180 s: A crack must appear in the crust that allows infiltration of the gas trapped between the steel and the solid, thereby increasing gas pressure. 3. t 5 240 s: The same phenomenon is observed. 4. 240 , t , 540 s: There is sublimation at the inner surface of the crust that increases the mass of gas in the gas blanket and therefore increases the pressure. URANIUM HEXAFLUORIDE BEHAVIOR IN FIRE icantly, thereby reducing the rise in pressure, or even slightly decreasing the pressure. 8. 880 , t , 1080 s: Once nucleate boiling is established over all the surface of the container, a bubbly thermal boundary layer forms along the inner metal surface. The energy absorbed by the liquid remains trapped within this boundary layer from which it is released at the liquid-gas interface ~Fig. 28!. Since the energy input is at the interface, condensation on the interface is reduced, and consequently the pressure increases. 6. 700 , t , 800 s: There is a change to transition boiling where the flux increases considerably ~Fig. 13!, as well as the production of vapor. A larger quantity of vapor reaches the gas pocket and so contributes to an increase in pressure. 9. 1080 , t , 4000 s ~see Fig. 30!: The heat transfer regime changes gradually to natural convection, where the generation of vapor falls rapidly, which should lead to a pressure drop. However, in natural convection, the convective velocities of the liquid in the boundary layer will be considerably less than during nucleate boiling. Similarly, the motion induced in the liquid pool is reduced, which reinforces the stratification and then decreases the vapor condensation. Note that boiling close to the free surface continues long after heating is stopped due to the thermal inertia of the furnace and of the steel at the top, producing the lateral thermal gradient described earlier ~Sec. II.B.1 and Fig. 15!. Despite the fact that the quantity of vapor arriving in the gas blanket decreases, the pressure continues to increase due to the simultaneous decrease in the quantity of vapor condensed. However, the decrease in the quantity of vapor evaporated is more rapid than the decrease in the quantity of vapor condensed, so that the pressure does not rise so sharply and reaches at ;4000 s a maximum ;32 bars with P2 or 27 bars by extrapolating P1. 7. 800 , t , 880 s: Nucleate boiling replaces transition boiling, and the generation of vapor drops signif- 10. t . 4000 s : There is no more boiling, and the pressure gradually decreases under the effects of 5. 540 , t , 700 s: At 540 s, the collapse of the UF6 solid top crust allows film boiling to develop. In this boiling regime, a relatively large quantity of vapor is generated, although pressure increases only slightly. This indicates that there must be considerable condensation of the vapor produced at the boiling surface. Because of gravity forces, in the lower part of the container, the bubbles detach from the vapor film as shown on Fig. 28. These bubbles condense in the subcooled liquid and on the solid, thereby releasing their energy to the liquid. In contrast, in the upper part, the vapor film is stable and a large quantity of vapor arrives in the gas pocket. If the pressure does not increase, this means that a large amount of this vapor condenses at the liquid-gas interface. Fig. 30. Pressure evolution from 0 to 10 5 s. NUCLEAR TECHNOLOGY VOL. 127 SEP. 1999 347 Pinton et al. URANIUM HEXAFLUORIDE BEHAVIOR IN FIRE Fig. 31. Position of the thermocouples on the median plane. condensation of the vapor at the interface and thermal leakage from the furnace. III. INTERPRETATION OF THE TEN4 TEST AND COMPARISON WITH THE TEN2 TEST The TEN4 test carried out on February 5, 1996, consisted of a high-temperature heating test for an internal configuration of UF6 similar to the one existing just after its filling. Indeed, the initial state of the UF6 during the 18-min TEN2 test did not correspond to this case because the container had already undergone a heating of 10 min 7 days previously. As compared to the TEN2 test, the instrumentation has undergone some modification since different interrogations have been raised ~symmetry, edge effect, etc.!. Some measurements were displaced. Especially, the number of thermocouples on the median plane of the container was increased as indicated in Fig. 31. Figures 32 through 35 show that the general evolution of the different measurements of TEN4 were identical to TEN2. Most of phenomena met with TEN2 were reproduced in TEN4. For this reason, the detail of the TEN4 interpretation is not resumed. Only some observed differences will be discussed. For example, there is a small shift of ;200 s because of the initial temperature difference, i.e., colder in TEN4 ~178C! than in TEN2 ~368C!, and a radiant flux slightly weaker in TEN4 than in TEN2. This difference of flux seems to come from a variation of the outer surface state of the container. In fact, before being sanded, the container TEN2 was covered with a paint while TEN4 was in the manufactured state. It is possible that paint particles have remained on the steel, modifying the absorption of the infrared radiation of TEN2 when compared to TEN4. Note that Figs. 32 and 33 show that up to 500 s of heating, the UF6 solid temperature has not practically increased. On the other hand, from 500 to 700 s, the UF6 temperature has increased 158C on average from the initial temperature. This behavior may be due to internal tubes that disturb measurements in the solid UF6 . At ;500 s, the pressure is such that the gas can penetrate the cracks existing in the solid and mainly near the tube. This explains the observed increase locally. This would mean that Fig. 32. Temperature evolution of the UF6 in the upper part of the median plane. 348 NUCLEAR TECHNOLOGY VOL. 127 SEP. 1999 Pinton et al. URANIUM HEXAFLUORIDE BEHAVIOR IN FIRE Fig. 33. Temperature evolution of the UF6 in the bottom part of the median plane. Fig. 34. Evolution of the steel inner temperatures in the median plane. temperatures measured in the solid do not reflect the UF6 global profile but remain local indications. IV. INTERPRETATION OF TEN6 TEST AND COMPARISON WITH TEN2 AND TEN4 The TEN6 test, undertaken June 13, 1996, concluded the Tenerife program. The container was heated NUCLEAR TECHNOLOGY VOL. 127 SEP. 1999 to 8808C during 18 min. It had the objective of establishing a radiative flux close to that of an IAEA fire. The physical phenomena are somewhat identical to these of TEN2 and TEN4. This is why the interpretation of TEN6 is not detailed. However, for TEN2 and TEN4, the liquid rapidly wets all the metallic wall after rupture of the upper crust, and transfer into the boiling regime develops very rapidly. On the contrary, for TEN6, wetting of the wall is progressive. 349 Pinton et al. URANIUM HEXAFLUORIDE BEHAVIOR IN FIRE Fig. 35. Pressure evolution. The quantity of vapor arriving in the gaseous region is smaller, and the liquid stratification is delayed. A consequence is the delay in pressure increase reported in TEN2 and TEN4 tests. This phenomenon can have several origins: 1. different initial configuration and solid internal structure 2. variable contact resistance 3. nonhomogeneous radiative heat flux. In the current state of the study, no leading hypothesis can be identified. on the steel wall. Reasons for this phenomenon are unknown at this time. V. CONCLUSION 2. E. PINTON, “Modelisation du comportement d’un conteneur d’hexafluorure d’uranium soumis à un feu,” PhD Thesis, Institut National Polytechnique de Grenoble ~Nov. 1996!. A considerable improvement in the knowledge of heat and mass transfer and internal physical phenomena has been obtained thanks to tests carried out on containers filled with UF6 . The main points are as follows: 1. The presence of a strong thermal contact resistance at the solid UF6-steel interface. 2. The rupture of the solid crust at a pressure near 1.5 bars ~triple point!. This leads to the initiation of boiling heat transfer and notably film boiling, followed by transition boiling and nucleate boiling. 3. The appearance of the liquid stratification with the appearance of nucleate boiling. It has the consequence of accelerating the rise in pressure because of the reduction of mass transfer by condensation to the liquidgas interface. This stratification is preserved with the natural convection regime that replaces the nucleate boiling after the end of the heating. 4. After rupture of the upper UF6 crust, the pressure increase may be delayed by different wetting of the UF6 350 Also, these tests permitted building and validating a scenario that has been reproduced in the numerical model developed by the CEA Grenoble ~France! about the behavior of a UF6 container under fire conditions.2 REFERENCES 1. “Recommendations for Providing Protection During UF6 Transport,” TEC-DOC0IAEA, International Atomic Energy Agency. 3. E. PINTON, B. DURET, and G. BERTHOUD, “Behavior of a UF6 Container During a Fire—II: Modeling and Validation,” Nucl. Technol., 127, 352 ~1999!. 4. SUZUKI et al., “An Experimental Study on Heat Transfer of a UF6 Filled Vessel,” presented at UF6 Safe Handling Processing and Transporting Mtg., Oak Ridge, Tennessee, May 24–26, 1988. 5. J. SAROUL et al., “TENERIFE Program Experimental Results,” presented at UF6 Conf.: Handling, Processing, and Transporting, Paducah, Kentucky, November 28–December 1, 1995. 6. R. DE WITT, “Uranium Hexafluoride: A Survey of the Physical-Chemical Properties,” GAT-280, Goodyear Atomic Corp. ~1960!. 7. J. C. ANDERSON, C. P. KERR, and W. R. WILLAMS, “Correlation of the Thermophysical Properties of UF6 ,” ORNL0ENG0TM-51, Oak Ridge National Laboratory ~Aug. 1994!. NUCLEAR TECHNOLOGY VOL. 127 SEP. 1999 Pinton et al. URANIUM HEXAFLUORIDE BEHAVIOR IN FIRE Eric Pinton ~Eng, heat transfer and energy systems, Institut Universitaire des Systèmes Thermiques Industriels, France, 1992; PhD, physics and energy, Institut National Polytechnique de Grenoble, France, 1996!, has studied the behavior of a UF6 container during a fire at the Commissariat à l’Energie Atomique ~CEA! of Grenoble; analysis and phenomenological interpretation of experimental results, numerical modeling, and validation of the DIBONA code; DIBONA code input parameter sensitivity; and improvement of the code user-friendliness at the French Institute for Protection and Nuclear Safety. Recently, he has been a design and project engineer at Robatel, where he works on design, certification, and manufacture of packaging and transporting of radioactive material casks. Bernard Duret ~Eng, thermal and chemical process, Institut de Génie Chimique de Toulouse, France, 1976! works in the thermohydraulic service of CEA Grenoble on topics bound to nuclear safety studies ~molten UO 2 propagation, corium ablation, radioactive containers during fire, etc.!. Georges Berthoud ~PhD, nuclear engineering, Institut National des Sciences et Techniques Nucléaires, France, 1973! has worked since 1976 in the Heat Transfer Laboratory at CEA Grenoble mainly in the area of multiphase multicomponent modeling. Presently he is the head of the Multiphase Multicomponent Laboratory in the Thermal Hydraulics Department. NUCLEAR TECHNOLOGY VOL. 127 SEP. 1999 351