ML20107C000
ML20107C000 | |
Person / Time | |
---|---|
Site: | Ginna ![]() |
Issue date: | 12/31/1984 |
From: | Abe Y, Iwamura T, Sobajima M JAPAN ATOMIC ENERGY RESEARCH INSTITUTE |
To: | |
Shared Package | |
ML17195B056 | List: |
References | |
JAERI-M-84-221, TAC-08350, TAC-8350, NUDOCS 8502210121 | |
Download: ML20107C000 (159) | |
Text
{{#Wiki_filter:- . - - - - - - - - - - - - - - - - - - - - - J AER I - M ~ 9 3.< , 1 84-221 1 l l l EFFECTS OF UPPER PLENUM INJECTION CN THERMO-HYORODYNAMIC EEHAVIOR UNDER REFILL AND RE.:LOCD PHASES l 1 l
. 1 December -1934 j Taxamichi IWA.\lCRA. \. lakoto 50BAJI.\ tA {
Yutaka ABE. Hiromichi ADACHI. Akira OHNUK! and . \tasahiro OSAKABE l l I l l P l b U M h 2 kh E 0/T Jccan Atomic Energy Resecach Institute
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JAERI-M 84-221 . Effects of Upper Plenu= Injection on Ther=o-Hydrodynamic Beharior Under Refill and Reflood Phases Taka=ichi IWAMURA, Makoto 503AJIMA, Yu:aka A3E, Hiro=ichi ADACHI Akira OH2.'JKI and Masahiro OSAG3E Depart =ent of Nuclear Safe:y Research, Tokai Research Establish =ent, JAERI ( Received November 7,1984 ) In order to investigate the churmo-hydrodynamic behavior in core under simultaneous ECC wa:er injec: ion into the upper plenum and the intac: cold leg during :he refill and reflood phases of a ?%R-LOCA. Tes:s SI-SH3 and SI-SH4 were performed by using Slab Core Tes: Facility (SCTF) with :he injec: ion of saturated and'67K subcooled water into :he upper plenu=, respec:ively, under the sa:e cold leg injec: ion condi:Lon. Th'e following =ajor findings were obtained by exa=ining these test results. (1) Although the core was cooled by the fall back water from the upper plenum into the core during the period of high injection rate into the upper plenum, the core was cooled =ainly by the bot:o= flooding , after the 30CREC (Sottom of core recovery). (2) The possible fall back flow rate esti=ated with a CCFL correlation rapidly decreased af ter the BOCREC because of the increase of steam generation rate in core. (3) Continuous fall'back of subcooled water was not observed even under the condition with large upper plenum injection race of subcooled water and with steam outflow through the lower plenum in:o the downcomer. The fall back<was intermit:ently 1Laited by the rapid increase of upward steam flow which was generated in the core due to the evaporation of the fall back water. (1) The rising of. liquid level in the lower plenum was suppressed by The work was perfor=ed under contract wi:h the Atomic' Energy Bureau of Science and Technology Agency of Japan i L-___ m_
JAERI-M 84 - 221 l the pressurization in core due to the evaporation of f all back water before the SOCRIC and therefore the beginning of botto= reficed was delayed. Sc=a selected data fro: Tests St-SH3 and 51-SHl. are also included in this report. Keywords: Reflood, Refill, LCCA, ECCS, PML, Combined Inj ection, '4ater Fall Back, Heat Transfer, Quench, Carryover, Two phase Flow , SCTT, Thermo-hydrodynamic Sahavior, Reactor Safety S 4
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J JAERI-M 84 - 221 Contents
- 1. Introduction ................................................. 1
- 2. Experiment.................................................... 2 2.1 Test Facility ............................................. 2 2.2 Test Conditions ........................................... 3 2.3. Test Procedure ............................................ 4
- 3. Test Results and Discussions ................................. 3 3.1 Boundary Conditions ....................................... 5 3.2 Fall Back Characteristics ................................. 6 3.2.1 Occurrence of Fall.3ack at End Box Tie. Place .......... 6 3.2.2 Two-Dimensional Fall Back Behavio r . . . . . . . . . . . . . . . . . . . . 7 3.2.3 Estimation of Fall Back Flow Rate ..................... 8 3.3 -Water Accumulation Behavior in Core ....................... 10 3.4 Fluid Behavior in Lower Plenum and Downco=er .............. 11 3.4.1 Water Accu =ulation Behavior in Lower. Plenum ........... \11 ,,
3.4.2 Estimation of Lower Plenum Flashing Race .............. 13 3.4.3 Water Accu =ulat ion Behavio r in Downcomer . . . . . . . . . . . . . . 14 3.5 Fluid Behavior in Ect Leg ................................. 14 3.6 Evaluation of Steam Outflow Race, Steam Generation Rate i1 in Core and Steam Condensation Rate in Upper Plenum ....... 15 3.7 Core Thermal Behavior ..................................... 16 3.7.1 Heater Rod Surface Temperature ........................ 16 3.7.2 Quench Characteristics ................................ 18 3.7.3 Heat Transfer-Characteristics ......................... 19
- 4. Conclusions .................................................. 21 Acknowledgment ................................................... 22 References ....................................................... 22 Appendix A Slab Core' Te st Facility (SCTT) Core-1 . . . . . . . . . . . . . . . . 68 Appendix 3- Selected Data of Test SI-SH3 (Run 528) ~.............. 114 Appendix C Selected Data of Test SI-SH4 (Run 529) ............... 133
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JAERI-M S4 -221 List of Tables Table 2-1 Comparison of dimensions between SCTF and 1,100 MWe PWR Table 2-2 Test conditions for Tests S1-SH3, S1-SH4 and 51-19 and calculated results for co=bined injection = ode for a reference PWR Table 2-3 Chronologies of events for Tests S1-SH3, 51-SH4 and 51-19 List of Figures Fig. 2-1 Schematic diagram of Slab Core Test Facility Fig. 2-2 Arrangement and dimension of UCSP water injection and extraction noz:les Fig. 2-3 Pressure vessel of Slab Core Test Facility Fig. 3-1 ECC water injection rates into intact cold les Fig. 3-2 ECC water injection rates into upper plenum Fig. 3-3 Temperatures of ECC vater injected into upper plenu= Fig. 3-4 Pressure transients in core center Fig. 3-5 Pressure transients at top of contain=ent tank-I
-Fig. 3-6 Core heating powers Fig. 3-7 Differential pressure across end box tie. place and fluid ta=perature just below end box tie plate above bundle 4 in Test 51-SH4 Fig.'3-8 -Fluid te=peratures.in upper plenus Fig. 3-9 Comparisons of fluid temperatures just below end box tie ~
plate and differential = pressures.across end box tie place over 8 bundles in Tes 51-SH3 Fig. 3-10 Cc=parisons of fluid temperatures just below end box tie place and differential pressures across and box tie plate over 8 bundles in Test S1-SH4 Fig. 3-11 Void fractions in Bundles 2,'4 and 8 at upper part of core
. Fig. 3-12 Horizontal differential pressures between Bundles 5 and S Fig. 3-13 Horizontal differential-pressures between Bundles 1 and 8 Fig. 3-14 Estimated fall back mass flow rates with CCFL correlation.
Fig. 3-15 Liquid levels in upper plenum Fig. 3-16 Vertical differential pressures'across core full height Fig. 3-17 Void fractions in core at six elevations
' Fig. 3-18 Liquid-levels in lower plenum Fig. 3-19 Fluid velocities.below core barrel vs
JAER!-M 84 -221 Fig. 3-20 Estimated penetration water flow race from upper plenum to lower plenum in Test 51-SHa Fig. 3-21 Void fraction in broken cold leg pressure vessel side in Test 51-SH4 Fig. 3-22 Flashing races in lower plenu= a Fig. 3-23 Liquid levels in downcocer Fig. 3-24 Mass flow rates'in four regions of hot les Fig. 3-25 Void fractions in four regions of hot leg
' Fig. 3-26 Steam outflow race through hot leg Fig. 3-27 Steam generation races obtained from heat balance calculation Fig. 3-28 Total steam generation rates obtained from heat balance and lower plenum flashing Fig. 3-29 Steam condensation race in upper plenum in Test 51-SH4 Fig._3-30 Heater red surf ace ce=peratures at elevations of 3.19, 1,905 and 0.95 s Fig. 3-31 Horizontal distributions of turnaround camperatures at elevations of 2.76, 1.735 and 0.52 =
Fig. 3-32 Quench e,nvelopes in Bundle ' Fig. 3-33 .Cc=parison of quench envelopes in all bundles
. Fig. 3-34 Radial distributions of quench times at elevations of 2.76, 1.735 and 0.95 s Fig. 3-35 A:imuchal distributions of quench ti=es at elevation of 2.76 m Fig. 3-36 Horizontal distributions of early quenched rods at elevation of 3.19 s in Tests Tests S t-SH3 and 51-SH4 Fig . 3-3 7 ' Heat transfer coefficients at 2.33 m in Sundle a Fig. 3-38 Heat transfer coefficients vs. distance from quench front at elevations of 2.76, 2.33,1.905 and 1.38 s in Bundle a Fig. 3-39 'Jacer fractions vs. distance from quench front at elevations of 2.76, 2.33,1.905 and 1.38 s in Bundle a . Fig. 3-40 Heat transfer coefficients vs. water fraction at elevations of 2.76, 2.33,1.905 and 1.38 s in Bundle 4 - vm
e JAERI-M 84 - 221
- 1. Introduction The ther=al-hydraulic behavior during the refill and reflood phases of a postulated loss of coolant accident (LOCA) in a pressuri:ed water reactor (?WR) has been investigated by using the Slab Core Test Facility (SCTF) which has an electrically heated core witn a full height, full radial width and azimuthal single-bundle depth. The SCTF program is a part of the large scale reflood test program under contract with the Atomic Energy Bureau of Science and Technology Agency of Japan together with the Cylindrical Core Test Facility (CCTF) program.
As an alternative Emergency Core Cooling System (ECCS), the combined injection mode in which the ECC water is si=ultaneously injected into both the hot leg and the cold leg is proposed in order to i= prove the core cooling by a large amount of fall back water into the core. The thermal-hydraulic behavior during the initial period of the co=bined injection mode was investigated in the present two preliminary tests: Tests S1-SH3 and 51-SH4, by injecting the ECC water into the upper plenum instead of the hot legs and into the cold leg in the SCTF Core-I test serics. These two tests were performed with saturated and subcooled water injection into the upper plenum and therefore the effects of injection water te=perature-can be investigated by comparing the results of these two tests. Since included in the purposes of these two tests were to confirm the perfor=ance of the upper plenum injection and extraction system and to establish the technical method of the co=bined injection tests planned in the SCTF Core-III test series, the test conditions were not
. necessarily appropriate for the simulation of the typical combined ~
injecrion mode for a PWR. However,. qualitatively useful information was obtained on the initial ther=al-hydraulic behavior in core particular to the combined injection mode. The present report describes the fall back behavior from the upper plenum into'the core, the water accu =ulation behavior in the core, the lower plenum and the downcomer, the fluid behavior in the pri=ary loops and the core cooling behavior. Presented in Appendix A are the brief description of SCTF and measurement locations. The st'ected data obtained in Tests S1-SH3 and S1-SH4 are presented in Appendixes 3 and C, respectively.
JAERI-M $4 -221 .
- 2. Experiment 2.1- Test Facility The sche =a:ic diagra= of SCTF and the comparison of di=ensions be:veen- the SCTF and a 1,100 MWe PWR are shown in Fig. 2-1 and Table 2-1, respectively.
The primary coolant loops consist of a hot leg equivalen: to the four actual hot legs, a steam / water separator corresponding to the four actual steam generators, an intact cold leg equivalent to the
'three actual intact cold. legs, a broken cold leg on the pressure vessel side, and a broken cold leg on the steam / water separator side. These two broken _ cold. legs are connected to two different contai= ment tanks.
The flow area scaling ratio is 1/21 to a 1,100 MRe PWR, whereas the height of each component si=ulates :he actual PWR, The emergency core cooling syste= (ECCS) consists of an accu =ulator (Acc) system, a low pressure coolant injection (LPCI) system, and an upper core super: place (UCSP) water injection systes. All of these three injection systens were used f or the co=bined injection pre-tests.
'The injection port for the Acc and LPCI systens is located on the intac:
cold leg and that for the UCSP water 'injec: ion system is the eight injec-tion nozzles located just above the UCSP for each bundle. The schematic of -the UCSP water injection system is shown in Fig. 2-2. As adjacent two nozzles are-connected into'one at the outside.of the pressure vessel, four lines in total are provided for giving the specified flow and -fluid temperature :ransients independently. Figure 2-3 shows-the vertical cross sec: ion of :he pressure vessel. The pressure vessel-includes a simulated core, an upper plenum with internals, a lower plenum, a core baffle and a downcocer. The simulated core consists of 8 bundles arranged in a row with
-full radial width. Each bundle consists of 234 hea:er rods and .22 Jnon-heated rods arranged in 16x16 array. The outer diameter and the heated length of the heater rod are 10.7 mm and 3660 ==, respectively. ~ The dimensions of rod bundle, such as the red pitch, the spacers, the end box-tie plate etc., are based on those for a 15x15. fuel rod bundle of a'?WR.
The core and the upper plenum are enveloped by honeycomb charmal insulators to minimize the vali effects. More detailed infor=ation on the RSCTF is available in reference (1)
.. J
LLERI-M 84 - 221 and brief description is presented in Appendix A. 2.2 Test Conditions In the co=bined injection = ode of an actual reactor, the subcooled water injected into the hot leg flows into the upper plenum and then falls on to the UCSP after hitting the upper plenu= internals. In the present combined injection pre-tests: Test 51-SH3 (Run 528) and Test
'SI-SH4 (Run 529), the fluid characteristics in the upper plenum was simulated by horizontally injecting the ECC water through the side nozzles and extracting from the other side notzles located just above -the UCSP as shown in Fig. 2-2.
The water subcooling in the upper plenum is esti=ated to be in the range of 20 to 40 K according to the calculated results for a reference PWR. -Since the water subcooling in the upper plenum is considered to affect .the f all back characteristics, the te=perature of upper plenum injection water was selected as a test parameter. That was almost saturated in Test 51-SH3 and subcooled of about 67 K with respect to the saturation temperature at 0.25 MPa in Test SI-SH4 so as to include che-calculated range of a reference PWR.
- These'.two tests were performed under refill and reflood simulation condition. The refill si=ulation test: Test S1-19 (Run 325), is referred as a counterpart test with cold leg _ injection mode. Major
. test conditions for Tests S1-SH3, 51-SH4'and 51-19 and the calculated results.for-a reference PWR are listed in Table 2-2. Chronologies of events for these three tests are listed in Table 2-3. The 30CREC in.
Tables 2-2 and 2-3 represents the time at the bottom of core recovery when'the ECC water reaches the bottom of heated part. , Tests SI-SH3 and_SI-SH4 were performed under almost the same conditions except the water temperature of UCSP injection system. The test conditions for Test S1-19 were almost the same as those for Tests
-St-SH3:and.SI-SH4 except that no UCSP' injection system was used and the . vent line . connecting the upper plenum and the downcomer was open in Test S1-19 while it was closed in Tests'SI-SH3 and SI-SH4.
As indicated in Table 2-2, the scaled upper pler.um injection race and cold leg injection race are larger in the present tests than in the cal'eulated results.during the Ace period. However, the Ace injection
~
time is much shorter and the LPCI flow rate is much lower in these two 3.-
o JAERI-M 84 -221 tests as. compared with the calculated results because one of the objectives of the present tests is to confirs the flow rate control function of.the UCSP injec: ion system under the lower flow rate condi-tion. Therefore it should be noted : hat the thermal-hydraulic behavior af ter 23 s from the ini:iation of upper plenum injection does not well simulate the thermal-hydraulic behavior under the typical co=bined injection = ode.
~
2.3 Test Procedure The test procedure for the combined injection pre-tests is as follows. After setting the initial conditions, core heating was initiated. At 100 s after the core power on, :he break valves were opened and the core power decay simulation started with the ini:ia: ion of UCSP vater injection and extraction system. The =axi=um cladding te=perature at
- his ti=e was' intended to be 995 K. The decay curve is simulated from 21 s af:er the shutdown of a Wes:inghouse type PWR. The decay curve is based on=:he "AIS Standard + Ac:inides + Delayed Neutron Effect for voided Core". '
At 105. s (Test SI-SH3)' or 103 s (Test $1-SH4) after the core power on, Acc-injec:ica.was. initiated into the intact cold leg. Af:er 23 s (Test St-SH3) or 21 s (Test' SI-SH4) from Acc injection, che Acc injec-tion was switched to LPCI. The maxi =us Acc and LPCI flow rate were about 84.kg/s and'S kg/s, respec:ively. The' :otal UCSP water injec: ion rate was incended :o be about 100 kg/s during the first 23 s and about 11 kg/s :hereafter wi:h equal flow rate for each of eight UCSP injec: ion nozzles. However, the UCSP injec-tion line. connecting to the upper plenum above 3undles 1 and 2 did not open.during'the first 60 s for Test 51-SE3 accidently. The test was finished af ter 900 s from LPCI initiation. s-
JAERI-M 84 - 221 o
- 3. Test Results and Discussions 3.1 Boundary Conditions Figure 3-1 shows the co=parison of ECC water injection rates into
'the cold leg between Tests SI-SH3, 51-SH4 and S1-19. The Acc flow rate and injection' period and the LPCI flow rate are almost identical for these three tests.
Figure 3-2 shows the UCSP water injection rates into the upper plenum in Tests SI-SH3 and S1-SH4. As shown in Iig. 3-2(1), the UCSP
- vater injection-system above bundles 1 and 2 in Test St-SE3 did not work well. Through the nozzles above bundles 1 and 2 in Test St-SH3, no water _ was injected until 60 s af ter the break valves open and then 3
the UCSP injection started at very high flow rate up to 0.044 m /s.
~About 20 s later, the UCSP injection rate through these nozzles approached the nominal injection race. In Test St-SH4, on the other , hand, the same amount of water was injected into the upper plenum through all nozzles as shown in : Fig. 3-2(2) . 'The upper plenum. water was extracted through the UCSP extraction fnozzles above each bundle at the opposite side of the injection nozzles.
In these two tests, however, the UCSP water extraction system did not work' welliand the accuracy of the extracted water flow race is doubtful. 3 The:UCSP extraction syste= will be-improved in the later part of SCTF Core-II test: series. Figure 3-3 shows the temperatures of water injected into the . upper plenum in Tests St-SE3 and St-SH4. The saturation temperatures
- corresponding to the pressure at the top of upper plenum are also shown in. Fig. 3-3 for these'two tests. The.UCSP injection water temperature . -in Test S1-SH3 is about 405 K which is almost in agreement with the saturation temperature at .che : pressure in the upper plenum. The UCSP injection water: temperature in Test 51-SH4 is about 333 K above-bundles _1,' 2, 5 : and 6,' and about 3441K above bundles 3, 4, 7 and 8.
- The average subcoolings with respect to .the saturation temperature at the pressure in the upper plenum are ab'out 67 K and 56 ".
respectively. The temperature of _ cold l leg injection water is about 335 -K. in TejstsSt-SH3,'S1-SH4-and51-19. TheycomparisonsHof pressure transients at the center of coreEand-Y
~_ 5 -
JAERI-M 84 - 221 at the top of containment tank I are shown in Figs. 3-4 and 3-5, respectively. Although both of Tests SI-SH3 and SI-SH4 are che refill simula: ion
- ests with :he sa=e initial pressure of 0.54 MPa, the pressure at the center of core is higher in Tes: SI-SH3 than in Tes: $1-SH4 after the break valves open, indicating the condensa: ion of steam in Test 51-SH4 due to the higher subcooling of UCSP injection water in this test.
Core heating power cransients are identical for these three tests as shown in Fig. 3-6. 3.2 Fall Back Characteristics 3.2.1 Occurrence of Fall Back at End Sox Tie Place Figure 3-7 shows the dif ferential pressure across the end box cie plate, the fluid temperature just below the end box cie plate and the saturation te=perature above bundle 4 in Tes SI-SH4 The satura: ion te=perature was obtained from the average of two pressures seasured at the :cp of upper plenum and a: :he center of core. As shown in this figure, subcooled water is intersi::ently observed just below the end box tie place before the 30CREC, indicating that the subcooled water injected _into the upper plenum intermittently penetrates into the core through the end box tie plate before the 30CRIC. The intermittent and rapid decreases in fluid temperature are in many cases acco=panied by the significant decreases of differential pressure across the end box tie plate. As shown in Fig. 3-3, :he water in the upper planum is subcooled during the high flow race period of UCS'? injection and af ter : hat period the water temperature becomes almost saturated for Test SI-SH4. The maximum subcooling on UCSP is 39 K at 15 s after the break valves open. As listed in Table 2-2, during the inicial 28 s, the upper plenu= injection rate is higher than the calculated hot leg injec: ion rate in the :ypical combined injection mode for a reference PWR. In addition,
- he lower plenu= water level is below the bo::om of core barrel during this period as shown in Fig.'3-18. Therefore it is noted that even when :he upper plenum injec: ion rate and subcooling are large enough and the steam genera:ed in core can flow into the dcwncomer chrough the lower plenum.-the fall back of subcooled water does not continue for more :han 5 s and the saturated CCFL condicion is established again.
JAERI-M 84 -221 The reason why the continuous f all back does not occur is con-sidered that a part of fall back water is evaporated in core and the generated steam up-flow supports the weight of subcooled water. When the fall back is stopped, the stea= generation rate in the core decreases and therefore the steam up-ficw rate becomes lower than that corresponding to the CCFL break condition. The intermittent fall back behavior shown in Fig. 3-7 is probably attributed to the time lag between the fall back and the steam generation. 3.2.2 Two-Dimensional Fall Back Behavior Figures 3-9 and 3-10 show the comparisons of the fluid temperatures just below the end box tie place, the saturation temperature, and the differential pressures across the end box tie plate above Bundles I through 8 in Tests St-SH3 and $1-SH4, respectively. As shown in Fig. 3-9, the differencial pressures across the end box tie place in Test SI-SH3 inter =ittently show negative values during
- the initial 30 s except above Bundles 1, 2 and 3, while the differential pressures in Test 51-SH4 almost always show the positive values, suggesting that the amount of fall back water during this period is larger in Test SI-SH3 than in Test 51-SH4. The fall back water during.chis period promotes the cooling of upper core as will be discussed in Section 3.7.1.
The relatively. larger possitive differential pressure across the end box tie plate above Bundle 1 side in Test SI-SH3 is due to the 60 s delay of the UCSP injection above Bundles 1 and 2 as described in section 2.3. It is suggested from Fig. 3-10 that the intermittent fall back of
.subcooled water-t h rough the- and box tie place during the initial 40 s occurs nonuniformly over the eight bundles and simultaneous CCTL-break all over the eight bundles is not observed.
Figure 3-11 shows:the comparisons of void fractions in Sundles 2, .
-4 and 8 at the upper part of core in these two tests. These void fractions are calculated from the measured vertical differential pressures between core spacers by neglecting the effects of fricticnal and accelerational pressure drops. During the period from about 20 -to -
30 s, .the void fraction'is the lowest in Bundle 8 in Test $1-SH3 and - the void fraction is.the highest in Bundle 8 in Tesc $1-SH4. These
~
radial distributions in the void fractions are corresponding to those m
JAERI-M 84 - 221 in the' differential pressures across the and box tie place shown in Figs. 3-9 and 3-10 and then to the radial distribution 'in the fall back flow races. Figures 3-12 and 3-13 show the co=parisons of horiconcal differen-tial pressures between Bundles 5 and 8 and between Bundles 1 and 8 respectively, at the elevations of 1.905 m, 3.235 m and 3.821 m (just below the end box tie plate) f rom the bottom of heated length in these two tests. The positive differential pressure in these figures means that the pressure.in Bundle 5 or Bundle 1 is higher than the pressure > in Bundle 8. Before the 30CREC, the pressure in Bundle 8 is much higher than the pressures in Bundles 1 and 5 at the elevations of 3.235 and 3.821 m and
.che differential pressures between Bundles 5 and 8 and between Sundles 1 and 8 are relatively small at the elevation of 1.905 m in Test S1-SH3.
In Test 51-SH4, on the other hand, during the initial 40 s from the break valves open, the pressure in Sundle 8 is much lower than the
. pressures in Sundles 1 and 5 at the elevations of 1.905 and 3.235 m. ' The above-mentioned characteristics of horicontal' differential -pressures before the 30CREC indicate that the a=ount of fall back water is larger in Bundle 8 side in Test SL-SH3 and is larger in Bundle 1 i
side in Test St-SH4. This is consistent with the radial distribution of the subcool ci=e indication in fluid. temperatures below the end box tie place and the differential pressures across the end box tie place shown in Figs.:3-9 and'3-10 and also with the void fractions in the upper part of core shown in Fig. 3-11. The negative differential
-pressures between Bundles 1 and S and between Bundles 5 and 3 below the-end box tie place in Test 51-SH4 indicate . chat the direction of steam horizontal flow is from Bundle 8 to Sundle 1 even when the amount of_
f all ~back water is. larger in. Sundle 1 side.
- 3.2.3 -Estimation of Fall 3ack Flow Race The f all back water from the upper plenum into the core is considered to enhance the core cooling-especially for'the co=bined injection tests. In the present co=bined injection pre-tests, however, the fall back' flow race was not measured directly and was not estimated by the mass balance method.because the extraction flow race from the upper plenum could not be measured correctly. 'Therefore, an empirical
-s-
[.
JAERI-M 84 -221 CCFL correlation is used for the estimation of possible fall back flow race. The CCFL correlation is derived from the ' experimental data based on the.end box tie place which has the same vertical configuration as that . in the SCTF-1 with 1/72 scaled to the SCTF-I. The CCFL correlation for the SCTF-I tie plate is given by jo f' + j , s k'. = 1.25 (1) 5 - where
. jg =
- --A C g/gD(o f g
)] #
8 i = C:f/gD( f -: g)]
"f
- I.A W = Steam up flow rate W.t
= Water down flow rate (Fall back flow rate)
- = Steam density ~
8 Og = Water density D = Tie plate hole diameter (0.012 m) A = Total flow area in the place (0.2036 m )2 g = Acceleration due to gravity (9.30665 m/s2 ) The steam up flow rate, W , is assumed to be the summation of the
. .8 steam generation rate calculated by the heat balance method and the flashing rate in the lower plenum. The steam generation rate and the
- lower plenum flashing ' rate are shown in Figs. 3-28 and 22, respectively and the total steam generation rate is shown in Fig. 3-29.
Figure 3-14 shows the estimated fall back flow rates in Tests SI-SH3 and St-SH4. As shown in this figure, the maximum calculated f all back flow rate is seen before the BOCREC and af ter that time the fall back flow rate uis significantly reduced due to the increase of steam genera-tion rate in the core. It should be noted here that the following assumptions are made i for the estimation of fall back flow rates shown in Fig. 3-14.
~
(1)-Saturated CCFL is assumed even for Test St-SH4 in which subcooled
l JAERI- M 84 - 221 water is observed below the end box tie place as shown in Fig. 3-7. . (2) The fall back is assumed to occur unifor=ly over all bundles though there exists radial distribution in the f all back distributica as indicated in Figs. 3-9 and 3-10. (3) The stea= bypass flow f ro= the core into the downcocer through the lower plenum is neglected though the steam bypass flow is observed before the water level in lower plenum reaches the bot:om of core barrel as will be discussed in section 3.4.1. (4) The fall back flow rate is estimated regardless of the existence of water in the upper plenum. The assumptions (1) through (3) may result in underestimation of
.the fall back flow rate. As shown in Fig. 3-15, on the other hand, the collapsed liquid level in the upper plenum is reduced to very low level from 40 to '120 s, indicating that :he a=ount of water in the upper plenum is not enough :o fall back into :he core during :his period. ~
Therefore, the fall back flow rate is considerably overesti=ated after about 10 s in Fig. 3-14 A1: hough :he esti=ated fall back flow rate in Fig. 3-14 is not - quantitatively reliable due :o the above-mentioned reasons, it is qualitatively concluded that the fal'1 back flow ra:e is negliegibly small after the ini:iation of bot:om reflood. 3.3 'Jacer Accu =ulacion 3ehavior in Core Figure 3-16 shows the cocparison of vertical dif f erential pressure across the core full height between Tesrs SI-SH3 and 51-SHA. The differential pressures in these tests increase :e=porarily jus: af:er the intiation of ECC injection and then increase again after :he 30CREC. The comparison between these two tests indicates that the higher subcool-ing of the UCSP injec: ion water resul:s in the higher water accu =ulation rate in the core after the 30CREC. Figure 3-17 shows the co=parison of void frac: ions at six eleva-
- ions in the core. In general, the void frac: ions in Tesc $1-SH3 are higher than those in Test $1-SH4 excep: during :he period from 40 to 30 - s above the eleva: ion of 1.365 m. 3elow the elevation of 1.24 m, no water. accumulation is observed before the 30CREC. After the 30CREC, _
the void frac: ion is. higher in' Test $1-SH3 than in Test SI-SH4 at all elevations. _ to -
JAERI-M S4 -221 i The occurrence of fall back during the period from about 10 to 40-s is also indicated in Fig. 3-17 by the rapid decrease of void f fraction at the upper part of core. Although the amount of f all back water is negligibly small in these two tests during the period between 120 and 200 s as shown in Fig. 3-14, the void fraction in the core is lower in Test SI-SH4 than in Test St-SH3 during this period especially at the upper half of core as shown in Fig. 3-17. In addition, the generated stea= is condensed in the upper plenum at almost constant rate of about 1.4 kg/s during this period as shown in Fig. 3-29. Therefore, it is suggested that the higher water accumulation race in the core in Test St-SH4 is not caused by the fall back water but caused by the following reason: Since the
. steam out flow rate is =uch lower in Test 51-SH4 than in Test 51-SH3 due to the steam condensation in the upper plenum as shown in Fig. 3-26, the steam binding ef fect is also weaker in Test SI-SH4 The weaker steam binding effect results in the higher water accu =ulation rate in the core in Test S1-SH4 The higher water accu =ulation rate in the core in Test 51-SH4 results in the higher heat transfer coefficient and the lower cladding surface temperature at the upper half of core as will be discussed in Section 3.7.
3.'4 Fluid Behavior in Lower Plenum and Downcomer 3.4.1 Water Accu =ulation Behavior in Lower Plenum Figure 3-18 shows the liquid levels in the lower plenum in Tests S1-SH3, St-SH4 and S1-19. The liquid levels in the lower plenum in these three tests decrease just after the break valves open'due to the water flashing-caused by the rapid depressurization. The amount of flashing mass is estimated in the next section.
~ The 1 quid level in .the lower plenum reaches the boccom of core heating part at 80 s in Tests St-SH3 and S1-SH4 and at 19 s in Test 51-19. It is esti=ated that the beginning of bottom reflood is promoted by at most 2.5 s by the effect of open vent line for Test S1-19 and therefore the trend of earlier reflood for this test is not much affected by this difference in condition.
JAERI-M 84 - 221 The water accumulation behavior in the lower plenum in Tests S1-SH3 and Sl-SH4 is different with each other. The liquid level in :he ' lower plenum in Tesc $1-SH3 increases gradually even af ter the liquid level reaches the bot:om of core barrel at 50 s, suggesting that the driving force for the bottom flooding given by the downco=er water head is reduced by the pressurization in core due to the evaporation of fall back water. On the other hand, the liquid level in the lower plenum for, Test St-SH4 remains at 0.1 m below the bottom of core barrel until about 76 s and then increases rapidly. As shown in Fig. 3-19, the fluid velocity data obtained from drag disk flow meter located below the core barrel indicate that the direc-tion of fluid flow.is from the lower plenum :o the downco=er before the water level reaches the bottom of core barrel and after that ti=e :he direccion is reversed. The other evidences whi'ch indicate the outflow of water and steam from the lower plenum in:o the downcomer are presented below. A part of the f all back wa:er is expected to penetrate through the core and reach the lower plenum. The penetration water mass flow rate is obtained by subtrac:ing the steam genera: ion ra:e in the core from the fall'back flow rate. Figure 3-20 shows the estimated fall back flow rate, the steam generation rate and the penetration race in Test St-SH4. I: is found from Figs. 3-18 and 3-20 chat =ost of :he fall back water penetrates into the lower plenum while the water level in :he' lower plenum gradually increases until the wa:er level reaches -the bot:om of core barrel, indicating : hat the penetrated wa:er flows out into the downcomer during this period. A'part of'the steam generated in the core and the lower plenum is also expec:ed to flow through the bottom of core barrel into the down-comer before the water level reaches the bottom of core barrel. As shown in Fig. 3-21, the void fraction in the pressure vessel side broken cold leg indicates that the ECC water bypass occurs only before the bi-ginning of bottom reflood. Since :he ECC water bypass is caused by the steam up flow in the downcomer, it is evident that the steam also flows from the core into the downcomer before :he beginning of botton reflood. The steam generation race in the core is reduced af:er about 25 s as'shown in Fig. 3-27 and the average water head in dowaco=ar increases as shown in Fig. 3-23. At 76's in Test SI-SH4, the pressure balance between the core and :he downcomer breaks and the liquid level in the
JAERI-M 84 -221 , lower plenum rapidly increases up to the bottom of core level.
-From the view point of reactor safety, it is supposed that the upper plenum injection induces the fall back of water into the core before the 30CREC and the generated steam tends to prevent the reflooding from the botto=, though the initial' cooling is promoted by the upper plenus injection as will be discussed in section 3.7.1. Therefore, the upper plenum injection has two opposite effects on the core cooling.
3.4.2 Estimation of Lower Plenum Flashing Race Since the combined injection pre-tests were performed under the refill simulation condition, the rapid decrease of systes pressure induced the flashing of water in the lower plenum because the initial water te=perature in the lower plenu= was the saturation te=perature at the initial pressure of 0.54 MPa. The lower plenum flashing rate is calculated from the existing water and stea: = ass in the lower plenum and the depressurization rate by using the assu=ption of constant entropy process as follows: I [ _1I dS i dM. '
'3 .v [dS.' . (s Eg) sat 'E $.O lg dF sat "i dP sat dP -
de dM. The flashing rate, , is obtained by the following equation. dt
-/ d5 dS, dM E .. - ' I v I 1 3 S. (2) de -(S "g(_dP 'I dP de Zg),,e L sac sat. 'where (S ) = Specific entropy change due to evaporation, ' sat S = Specific entropy of saturated steam, S
g
= Specific entropy of saturated water, i P = Pressure.
M = Mass of steam in lower plenum, ,. M;- = Mass of water in' lower plenum,- i dP . p = Depressurization rate. k
JAERI-M 84 -221 The lower plenum flashing rates obtained by equation (2) for Tests S1-SH3 and SI-SH4 are shown in Fig. 3-22. The flashing rate is the highest just af ter the break balves open and then decreases. After the BOCRIC, the average flashing rate is less than 0.1 kg/s and negligibly s=all as co= pared wi:h the steam generation rate shown in Fig. 3-27. The lower plenum flashing rate is larger in Test SI-SH4 than in Test S1-SH3 just after the break valves open because the depressurization rate is. larger in Test S1-SH4 as shown in Fig. 3-4 During about 30 s before the 30CREC, however, the flashing rate is larger in Test St-SH3 because 'the water _ inventory in the lower plenum is larger in Test S t-SH3 as shown in Fig. 3-18 and the depressurization race is also larger in Test St-SH3 during this period as shown in Fig. 3-4, 3.4.3 Water Accu =ulation 3ehavior in Downce=er As shown in Fig. 3-23, the collap sed water levels in the downce==r in Tests St-SH3 and 51-SH4 increase gradually up to the final level of abou: 5.7'= and then re=ain at the sa=e elevation during :he tests. The final level is considered to be corresponding to the overflow level because :he liquid level in contain=ent :ank-I continues to increase during the test. The higher liquid level in Test St-SH3 af ter about 50 s.i;s attributed to the stronger. steam binding effect as suggested from the~ higher steam outflow ra:e shown in Fig. 3-26. On ':he other hand, :he collapsed water level in the downco=ar in Test $1-19 increases rapidly and af ter reaching :he peak of about 5.6 = the water level decreases and re=ains at 3.3 = f or about 250 s,.though
~
the ECC . water injection rates into the intac co1d leg are al=ost the same for-these three tests. 3.5 Fluid 3ehavior in Hot Leg Figures 3-21 and 3-25 show the comparisons of = ass flow rates and void _ frac: ions, respec:ively, at four ver:ical regions in the hot leg spool piece. Region I co= prises the upper 31
- of the pipe cross-sec:ional area, Region 2 co= prises the nex: lower 27 ", Region 3
' comprises the next lower 26 %, and Region 4 co= prises the bottom 16 *. ' These = ass flow races are calculated from the =easured densities and - drag f orces at each region by using :he -ho=ogeneous =odel.
JAERI-M 84 -221 The flow direction through the hot leg in Test SI-SH3 is positive and no flow reversal is observed. On the other hand, the flow
-reversal at Regions 3 and 4 is clearly observed in Test St-SH4 just 'before the BOCREC and at the later period of the test. The times when the void fractions in regions 3 and 4 decrease to al=ost 0.0 in Test 51-SH4 are in good agreement with the times when the flow reversal is observed in Fig. 3-24 The occurrence of hot leg flow reversal is confirmed by the flow observation through the view window at the lower part of hot leg. No flow reversal in Test 51-SH3 is due to the higher steam flow rate as shown in Fig. 3-26. -
3.6 Evaluation of Steam Outflow Race, Steam Generation Rate in Core and Steam Condensation Race in Upper Plenum The steam outflow race through the . hot leg is obtained by subtract-ing the. flashing rate in the steam / water separator from the summation of the steam mass flow race from the steam / water separator to the contain-ment tank-II an,d the steam mass flow race from the steam / water separator to the downcomer through the intact cold leg. The flashing rate in the steam / water separator obtained by the same method as described in sec-tion 3.4.2-is negliegibly small as compared with the total steam outflow As shown in Fig. 3-26, the steam outflow rate through the hot leg is significantly higher in Test SI-SH3 than in Test St-SH4, suggesting that considerable amount of steam is condensed in the upper plenum in
. Test 51-SH4 due to the subcooled water injection into the upper plenum.
Figure 3-27 shows the steam generation races in the core in these two tests. The steam generation race _was obtained from the heat balance calculation in the whole core. Additional steam is generated by the lower plenum' flashing during the depressurization period as shown in Fig. 3-22. Figure 3-28 shows the total-steam generation rates obtained by the su=mation of these two steam generation rates. As shown in-this
. figure, the total steam generation race'af ter the BOCREC is slightly larger 1in Test SI-SH4 than in Test $1-SH3, whereas the total-steam mass.
outflow rate is ': mach larger in Test S1-SH3 than in Test 51-SH4 as shown in' Fig. 3-26 because a part-of the generated steam is condensed in the upper plenum in Test S1-SH4- due to the higher subcooling of UCSP -injec-tion water. .In addition, during _the first 50 s in Test Sl-SH3 and s_._
JAER!-M 84 -221 the first 80 s in Test SI-SH4, some amount of the generated steam flows directly into the downcomer through the bottom of core barrel as indicated in Fig. 3-18. Figure 3-29 compares the two steam condensation rate in the upper plenum in Test SI-SH4 esti=ated by the dif ference between the total steam generation rate in the core and the steam outflow rate through the hot leg and estimated by the following equation: W.n3 i . up C p AT sub g , (3) ge d. tg where, W = Steam condensation rate, e
- W. . = Upper plenum injection rate, inj up C = Specific heat of water, 1T = Subcooling of the injected water, sb = Latent heat of evaporation.
H,g Equation (3) is derived from the assumption that the whole amount of injected water into the upper plenum becomes saturated due to the condensation of steam. Since the fluid temperatures in the upper plenum are almost saturated except.during the first 28 s as shown in Fig. 3-8, the calculated steam condensation rate is plausible after about 30 s from the break valves open. As shown in Fig. 3-29, the dif ference between the total stea= generation race and the steam outflow rate agrees well with the calculated steam condensation race with Eq. (3) after 120 s. The condensation rate in the upper plenum is about 1.4 kg/s after the 30CREC. The steam condensation in the. upper plenum results in,the higher water accu =ulation rate in the core for Test St-SH4 as discussed in section 3.3. 3.7 Core Thermal Behavior 3.7.1 Heater Rod Surface Temperature , I Figure 3-30 shows the comparisons of heater rod surface temperatures at the elevations of 3.19, 1.905 and 0.95 m from the bottom of heated
=
JAERI-M 84 -:01 length between Tests S1-SE3 and SI-SH4. These temperatures are measured at the center rods of Bundle 4 which are not adjacent to non-heated rods. During the first 30 s, the heater rod is cooled especially at the upper part of core in these two tests by the fall back water during this period. The initial cooling of heater rod is slightly larger in Test'SI-SH3, indicating that the initial fall back flow rate is larger in this test during the first 30 s. However, the core cooling is more enhanced in Test 51-SH4 than in Test SI-SH3 except the initial period. Consequently, the turnaround temperatures are lower and the quench times are shorter in Test S1-SH4. The cooling enhancement in this test is attributed to the higher water accu =ulation rate in the core as discussed in section 3.3. It is observed in Fig. 3-30 that the heater rod at 3.19 m in Test SI-SH4 is quenched at about 20 s and then increases again. The same temperature behavior is observed in 11 rods out of 57 instrumented heater rods as shown in Fig. 3-36. Figure 3-30 also indicates that although the upper part of core
-is cooled by the f all back water during the first 30 s, the core is mainly cooled by the bottom reflood af ter the 30CREC.
In orde- to investigate the two-dimensional effects on core ther=al behavior, the horizontal distributions of turnaround temperatures at the elevations of,2.76, 1.735 and 0.52 m are compared in Fig. 3-31 for these two tests. At the lowest power bundles, Bundle 7 and 8, the turnaround temperatures are lower in comparison to those at the other bundles for these two tests in accordance with the radial power profile. The relatively higher turnaround temperatures in Bundles 1 and 2 in Test SI-SH3 are due to the delayed injection into the upper plenum above these bundles as mentioned in section 3.1. In Bundles 6, 7 and 8, the turnaround temperatures in Test SI-SH3 are lower than thosa in Test S1-SH4, while those in Test St-SH3 are higher than those in Test SI-SH4 in the other bundles, indicating that the amount of initial fall back water into the core is relatively large at the Bundle 8 side in Test S1-SH3 due to the non-uniform UCSP injection during the first 60 s. The maximum turnaround temperature is 1158 K at 1.735 m in Bundle 1 in. Test Sl-SH3 and 1119K at 1.735 m in Bundle 6 in Test Sl-SH4. L.
JAERI-M 84 -221 3.7.2 Quench Characteristics The quench envelopes at the central rods in Sundle 4 are co= pared in Fig. 3-32 among Tests Sl-SH3, SI-SH4 and S1-19 with respect to time after the 30CREC. At the upper half of core, the quench occurs earlier in Test SI-SH4 than in Test SI-SH3 while no dif ference is observed in the quench times at the lower half of core between these two tests. The quench times af ter the BOCREC in Test S1-19 at the lower half of core are in good-agreement with those in the combined injection pre-tests. At the upper half of core, on the other hand, the quench times in Test SL-19 are later than those in Tests SI-SH3 and SL-SH4. Figure 3-33 shows the comparisons of quench envelopes at the central rods in all bundles in these three tests. As shown in this figure, the quench front proceeds upward from the bottom of core up to the elevatien of 3.19 m and the downward propagation of quench front f rom the top of core is li=icted above this elevation in =ost bundles in these tests. The upward quench propagation is approximately one-dimensional in spite of the radial power distribution, whereas the downward quench proceeds often nonuniformly. Figure 3-34 and 3-35 show the comparisons of radial and azi=uthal distribut'.sns of the quench- times af ter the break valves open, respec-tively. As shown in these figures, early quenches at the elevation of 2.76 s are more of ten observed in Bundles 1 and 3, or at the locations adjacent to the side walls. In addition, the effect of radial power profile on the quench times ,is slightly observed in Fig. 3-34 except at the elevation of 2.76 m in Test St-SH4. .Therefore, it is suggested that the distribution of water fall back is much affected by the existance of side walls than by the radial power profile itself. Figure 3-36 shows the horizontal distributions of earlier quenched rods at the elevation of 3.19 m in Tests SI-SH3 and $1-SH4 The earlier quenched rod is defined as the rod which experienced the quench before the 30CREC. Some charmoccuples at this elevation indicate the earlier . -quench and dry out. Those rods are also shown in Fig. 3-36. As shown in this ' figure, the earlier quench tends to occur at the locations adjacent to the side wells and the earlier quench also tends to occur-acre easily at the UCSP injection side than at the UCSP JAERI-M 84 -221 extraction side. However, the effect of radial power profile is not recognized in the distribution of earlier quenched rods. It is concluded from the above-mentioned quench characteristics that the upper plenum injection promotes the quench at the upper part of core and especially at the locations adjacent to the walls. And furthermore, the higher subcooling of the UCSP injection water promotes the earlier quench at the upper half of core. 3.7.3 Heat Transfer Characteristics Figure 3-37 shows the transients of heat transfer coefficients at the elevation of 2.33 = in bundle 4 in Tests SI-SH3, St-SH4 and S1-19. The heat transfer coefficients are calculated with a heat transfer calculation code 'TEAIT"( } developed for the SCTF test analysis. The heat transfer coefficients in Tests S1-SH3 and SI-SH4 temporally increase during the higher upper plenum injection period due to the initial fall back as already =entioned and then remain at low values until the beginning of botto= reflood at 80 s. A2terthat ti=e, the heat transfer coefficients increa'se again due to the water splahsed up from_the bottom quench front. In order to'=ake clear the heat transfer characteristics, the heat transfer coefficients at the elevation of 2.76, 2.33,1.905 and 1.38 m
'in bundle 4 are plotted against the distance from bottom quench front in Fig. 3-38. At the upper half of core, the heat transfer coefficient is higher in Test St-SH4 chan in Test SI-SH3 when the distance from bottos quench' front is more than about 0.5 to 0.8 m while no difference is observed within 0.5 = from the quench front. At the elevation of 1.38 m, on the other hand, the heat transfer coef ficient is higher-in Test SI-SH3 than in Test 51-SH4 within about 0.6 m from the bottom quench front while it is higher in Tese S1-SH4 above 0.6- m f rom the bottom . quench front.
The heat transfer coefficient in Test S1-19 is lower than both in' Tests St-SH3 and 51-SH4 except the initial peak caused by the oscillation of water level. The initial peaks of heat transfer.coeffi-cients observed in Tests- S1-SH3 and Sl-SH4 in Fig. 3-37 are not seen in Fig. 3-38 because the bottom quench fronts are not established unt11 80 s. The difference of heat transfer coefficient between the cold leg and combined injection tests becomes smaller with approaching the quench L JAERI- M 34 - 221 front. At the elevation of 1.38 m, the heat transfer coefficient is higher in Test $1-19 chan in Tests St-SH3 and 51-SH4 when the distance
-from botto= quench front is more than 0.6 s.
The . local water fractions at the elevations of 2.76, 2.33, 1.905 and 1.38 = in these three tests are plotted against the distance from bottom quench front in Fig. 3-39. The local water fractions are obtained by the interpolation of the water fractions calculated f ro= the vertical differencial pressures measured between core spacers. As shown in this figure, the local water fraction is much higher in Test S1-SH4 than in both Tests St-SH3 and St-19 at each elevation with respect to the distance from bottom quench front except the inital peak observed in Test St-19 which is caused by the initial oscillation of liquid level in core. The local water fractions in Test St-SH3 al=ost agree with those in Test 51-19 at the same distance from bottom quench front especially at the lower half of core. Figure 3-40 shows the relation between the heat transfer coeffi-cient and the local water f raction at the elevations of 2.76, 2.33, 1.905 and 1.38 s in these three tests. As shown in this figure, the heat _cransfer coefficient in Test 51-19 is rather close to that in Test 151.-SH3 if. the local water fraction is the same especially at the elevations of 2.76 and 2.'33 m, though the heat transfer coefficient in Test Sl-SH3 is higher than that in Test S1-19 if the distance from quench front is the same as shown in Fig. 3-38. On the other hand, the heat transfer coefficient in Test Sl-SH4 is lower than those in Tests S1-SH3 and 51-19 at the higher water fraction. The water fractions at the quench front are about 0.25 in Tests Sl-SH3 and S1-19 and about 0.3 in Test'Sl-SH4 at the elevations of 2.33 and 2.76 m. It is therefore suggested that the heat transfer characteristics , for the combined injection pre-tests are similar to chose for the cold leg injection test with respect to the local water f raction when the temperature of water injected into the upper plenus is nearly saturated. When the upper plenu= injection water has large subcooling, . however, tne heat-transfer characteristics in the core are different from those for .che cold leg injection test. Y
JAERI-M 84 - 221
- 4. Conclusions Test results obtained from the combined injection pre-tests:
51-SH3 (saturated water injection into the upper plenum) and Sl-SH4
~
(subcooled water injection into the upper plenum), were evaluated and the following results were obtained. (1) Continuous fall back of subcooled water was not observed even under the condition with large injection race of subcooled water into the upper plenum and with steam outflow through the lower plenum into the downcomer. The fall back was intermittently limited by the rapid increase of upward steam flow which was generated in the core due to the evaporation of the f all back water. (2) The fall back occurred nonuniformly over the eight bundles.
~
(3) The possible fall back flow race esti=ated with a CCFL correlation rapidly decreased af ter the 30CREC because of the increase of steam generation race in the core. (4) The higher subcooling of the upper plenum injection water resulted in the cooling enhance =ent especially at the upper part of core due to the following re son: Since the steam out flow rate was much lower due to the steam condensation in the upper plenum in the test with higher subcooling of upper plenum injection water, the steam binding effect was weaker and therefore the water accumulation rate in the core was higher in this test. (5) The rising of liquid level in the lower plenum was suppressed by the pressurization in the core due to the evaporation of fall back water before the 30CREC and therefore the beginning of bocco= reflood was delayed. (6) The mass outflow through the hot leg was larger in the test with saturated upper plenum injection water and no flow reversal in the hot leg was observed in this test, while significant hot leg flow reversal was observed in the test with subcooled upper plenum
-injection water.
(7) Although the core was cooled by the fall back water during the period of high' injection race into che upper plenum, the core was
=ainly cooled by the bottom reflood af ter the 30CREC.
(8) No significant.effect of radial power profile was recognized on the core cooling behavior before the 30CREC, but the core cooling was
. clearly promoted in the rods adjacent to walls.
L
, JAERI-M 84 -221 Acknowledge =ent The authors are =uch indebted to Dr. M. Nozawa, Dr. K. Hirano and Dr. Y. Murao for their guidance and encouragement for this progrs=.
They would like to express their appreciation to Mr. T. Iguchi, Mr. K. Okabe, Mr. J. Sugi=oco, Dr. H. Aki=oto, and Mr. T. Okubo of CCTF Enalysis group for their useful discussions. References 9 (1) H. Adachi, et al. , Design of Slab Core Test Facility (SCTF) in Large Scale Reflood Test Progra=, Part I: Core-I, JAERI-M 83-080 (1983). (2) M. Osakabe and Y. Sudo. ,- Heat Transf er Calculation of Si=ulated Heater Rods throughout Reflood Phase in Postulated P%*R-LOCA Experi=ents, J. of.Nucl. and Tech., Vol. 20, No. 7, pp. 559 - 570, (1983). (3) H. Adachi,. et al. , Cold Leg Injection Reflood Test Redults obtained in SCTF Core-I under Constant Syste= Pressure, to be published
'JAERI-M 84 - 221 r
Table 2-1 Comparison of dimensions between SCTF and 1,100 MWe PWR Item SCTF PWR (SCTF/ R) Quantity ot iiundle 8 143 1/24.1 Number of Heater Rx 187' W 3 72 1/21.0 Number of Rads 2048 a 14 2 5 1/21.2 Effective Length ut 1660 3660 1/1 Heater Rod (mm) Rod Pitch (mm) 14.30 14.30 1/1 Diameter ot' Heater Rod (rmt) 10.70 10.72 1/1 Diameter of Unheated Rod (mm) 13.80 13.87 1/1 Flow Area of Core (m2 ) 0.259 4 .76 1/17.7 Ef f ective Core Flow Area Based on the Measured 0.35 4 .76 1/13.b Level-Volume Rela e ionsh ip (m# ) Fluid Volume of Core Enveloped 0.92 17.95 U 19 . 5 by Honeycomb Insulators = Fluid volume of Lower 29.62 1/22.7
- 1. 305 Plenum (m )
Fluid Volume of Upper U .8 6 19.8 1/23.0 Herd (m ) Baf fle Region Flow Area (m2 ) 0.10 - 1.76 1/17.6 Upper Plenum Fluid Volume (m3 ) 1.16 23.8 1/20.5 2 Downcomer Flow Area (m ) 0.121 2.47 1/20.4 UCSP Thickness m) 76 76 1/1 Steam Generator Inlet, Plenum 0.931 4.25=4 1/18.3 St:malator Volume (m ) Height of Steam Generator 1.595 1.595 1/1 Inlet Plenum St::ulator (m) Flow Area at the Top Place of-Steam Generator Inlet Plenum 0.19 4.0 1/21.2 Sinulator (m3 ) Major Ar.is Length of Hot Leg 737 736.6 1/1 Cross Sectton Flow Area of Hot Leg (4 Loops) 0.0826 1.704 1/20.6 Flow Area of Intact Loop (3 Loops)- 0.059e 1.149 1/16.5 Flow Area of Becken Cold 0.0179 Leg (=2) 0.38 3 1/21.4
- Fluid Volume of Cere Including Caps between Core Barrel- and 1 . 14 Pressure vessel Wall JAER'l-M 84 -221
' Table 2-2 Test conditions for Tests St-SH3', 51-SH4 and S1-19 and calculated results for combined injection mode for a reference PWR Test St-SH3 Test St-SH4 Test 51-19 Calculated results (Run 525) (Run 529) (Run 525) for a reference combined injection hitial pressure Core center. 0.54 MPa 0.54 MPa 0.59 MPa -
Containment-I 0.21 MPa 0.21 MPa 0.22 MPa 0.4 MPa Upper plenum or hot leg. injection condi-tion - Injection rate 81 kg/s 97 kg~/s - 2000-1200 kg/s (Acc) Injection ci e 23 s 28 s - about 150 s (Acc)' Injection rate 11 kg/s 11 kg/s - - (LPCI) Subcooling about O'K 67 K - 20-40 K Cold leg injection condition Injection race 84 kg/s 84.5 kg/s 87.5 kg/s 1500-900 kg/s (Acc). Injection rate S.2 kg/s 3.2 kg/s 7.3 kg/s - (LPCI) Acc -Injection ti=e 27 s 24 s 24 s about 150 s
'Jacer ce:perature 335 'E - 334 K 339 K 303 K (Acc)
Water temperature 335 K 337 K-- 337 K -
'(LPCI)
Equivalent value for a reference P'4R
- Upper plenum injection rate during Acc period 2076 kg/s c** Cold leg injection rate during Acc period
.1316 kg/s l
l
- j
JAERI-M 84 - 221 r Table 2-3 Chronologies of events for Tests S1-SH3, S1-SH4 and S1-19
- (1) Test $1-SH3 Time after core Time after break power "0N" valves open Core power "0N" 0 see -101 see Core power decay initiation 101 0 and break valves open USCP injection and extraction initiation 101 0 Acc injection initiation 105 4 Maximum ECC injection rate (84 kg/s) 120 19 ' Switch-Acc to LPCI 128 27 .
30CREC 181- 80 Maxt:num core temp. (1158 k) 208 107 Wole core quenched 532 431
+
4 9 E, 4, e m
E-JAERI-M 84 - 221 (2) Test S1-SH4 - Time after core Time after break power "05" valves open Core power "0N" O see -100 see
-Care power decay initiation 100 0 (nd break valves open 1
- USCP injection and extraction' initiation 100 0 Acc injection initiation 103 3
' >!axi:num ECC injection rate (83 kg/s) 12a 2a 2 Switch Acc to LPCI 121 24 I- 30CREC 181 81 -.%ximum core temp. (1119 k) 190.5 90.5 y
Enole core quenched- 189 - 389 e E ['. JAERI-M 84 -221 (3) Test $1-19 Time after core Time after break power "0N" valves open Core power "0N"- O see -138 see Core power decay initiation 138 0 and break valves open Acc injection initiation 142 4 Maximum ECC injection rate (87.5 kg/s) ~156 18 BOCREC 157 19 Maximum core temp. -(1195 k) 160 22
' Switch Ace to LPCI. 163 25 Whole core quenched 578 440~
1 t
.- "f ,+
4 t + 4-.. - -v-s., . . , -- ,, . , , , - - ,,,;-. -,.
JAERI:-M 84 - 221 . Intact cold leg injection Intact cold leg Hotleg A Broken cold leg UCSP iniection / -S/W separator side
- = =@
O W> x@ u UCSP extraction
- b I , ></N v
@ Equaling line a
v Lower . plenum injection Broken cold leg-PV side
@ Pressure vesel @ Break valves @ Steam / water separator @ Flow resistance simulators tanks @ Containment @ ' Pump simulator Fig. 2-1 Schematic diagram of Slab Core Test Facility - 2s -
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JAERI-M 84 - 221
.io' 50 , , ; j j ". Test SI-SH3
{ 3 above Bundles 1 and 2 4 40 ' s above Bundles 3 and 4 ~* R _ F + above Bundles 5 and 6
'e -. Break valves open s acove Bundles 7 and 8 I m -
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. t o-5 50 - i !TestSI-SH4! j - . I 1 - 40 -
5 above Sundles 1 and 2 d a above Sundles 3 and 4 4 w , i + above Bundles 5 and 6
- 9
+
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Fig. 3-2 ECC va:er injec: ion ra:es into upper plenum JAERI-M S4 -221 450 TEc' SI-S O SATbRATIO["* WATER INJECTION , igm . 1 3 injection valve OPen - 3dNC'53 3 ONU d
- mND o
' X SUNCL-g for Buncles 1 and ., o ggy;;ge 7 ggg g $ 400 J-- - ~ ^
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/ ' I g i BOCREC $ Break valves open
[ . injection valves open , _
- for Bundles 3 though 8 o 350 o
a 1,L. 500
~
0 100 200 300 400 500 600 TIME (S) 450 TEST SI-SH4 SUSC00 LEO WATER INJECTION o sgr. TEnp,
- a SUNCLES 1 ANO 2 - % i - SUNCLES 3 AND 4
[ X SUNCLES S AND S _ 0 SUNOLES 7 AND 8
$ 400 -
v -l 0 - ; 2 m .- .
= =
w ' BOCREC . w I ,
> g i i I a *50 _- - L- M =; .
3: :: ::,' m u. Break valves open 300 0 100 200 300 400 500 600 TIME (S) Fig. 3-3 Temperatures of ECC water injec:ed into upper plenum fL JAERI-M 84 - 221 0.8 , i _
- ! l
~
PRESSURE IN CORE CENTER __3 0.S ,
; ; O TEST S1-SH3 : . A TEST S1-SH4 - >\'
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00 300 400 S00 S00 0 100 200 TIME (S) l 08 . g ; _ L , 0.S PRESSURE IN CORE CENTER _- O TEST S1-19
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00 400 0 100 200 300 SCO SCO TIME (S) Fig. 3-4 Pressure transients in core center JAERI-M 84 -221 04 ; , , j PRESSURE IN CONTRINMENT TANK I~ _ O TEST S1-SH3 ~ A TEST SI-SH4
~ ,
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TIME (S) 0.4 , , ,
~ .' PRESSURE IN CONTAINMENT TANK I_ ! O TEST S1-19 -
l I I i l
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{02 - BOCREC Break valves open j j - I i l f O 100 200 300 400 600 600 TIME (S) Fig. 3 Pressure transients at top of containment tank-1
JAERI-M 84 -221 1250 , , , . CORE HEATING POWER
. TEST SI-SHS 1000 E ~~'
O SUNCLES 1 AND 2 i \
\ A SUNOLES 3 AND 4 + SUNOLES 5 AND 6 g 750 N X SUNCLES 7 AND 3
- p = - W t w g 500 ----
- m. --
a- Break valves open , j i ! 4 . 250 -
- -h ' . !' I i
0 100 200 300 400 500 500 TIME CSI 1250 CORE HEATING POWER TEST SI-SH4 1C00 [. X O SUNCLES 1 QNO 2 A SUNOLES 3 AND 4 r a SUNCLES 5 AND 8 X !UNOLES 7 AND S g 750 -j -
~
3 - . 3 500 -. Break valves open . 250 -- - - - - -- -- --- 3 100 200 300 400 500 SCO TIME C51 1250 CCRE HEATING POWER TEST S1-19 1C00 !
. I-- - --
C SUNCLES 1 AND 2 - I & 9UNOLES 3 AND 4 ( - SUNCLES 5 AND $ _ p X SUNCLES 7 AND 5 y 750 - ~ ~ ~ ~ - - - -~~~- --
= 3reak valves open -
w 2 --
@ 500 a.
250 - - - - - - - - - - - - - - - - - - - - - - -~ T-- 0 100 200 '300 400 500 SCO TIME (51 Fig. 3-6 Core hea:1::g powers
- 36 '
500 i i 2 - TEST SI-SH4
~
[ 3 above Bundle 5 M h e
- 450 - -
l b a - Differential pressure across end box tie plate g? 9 E - t E (1 J V"\ "
'\ ~ ~
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? J\) -r - ,w n2.nc4~,)')tvb.IwwlrAj^bG v
0 o 5
\ aturation temperature o : S m ~
y : k Fluid temperature below end box tie plate
~ ' ' ' ' ' ' ' ' ' 0 350 ' '
i
-1 0 50 BOCREC 100 150 Time of ter break valves open (sec)
Fig. 3-7 Differential pressure across end box tie plate and fluid temperature just below end box tie plate above bundle 4 in Test SI-Sil4
JAERI .\184 -221 450 f TESTSk-SH4 -
; i ABOVE BUNDLE S x ; 1 0 M FRON UCSP - l I ^ s ,r------ ---
5 400
. i !
h w d i I
- FLUID TEMP.
c - S AT. TEMP . RT TCP GF U.P . 3 350 m 80CREC 1 300 0 50 100 150 200 TIME AFTER BREAK (51 450 , t l ; TEST S'l-SH4 i ABOVE SUNOLE S
- O.25 M FROM UCSP 5 400
'.\
s .,f-I 9 ;
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- FLUID TEMP. ~
c g- - Sat . TEnP. RT TCP OF U.P . 3250 w I i SCCREC , e v see 200 0 50 100 15c TIME AFTER BREAK (51 450 ' ' TEST SI-SH4 RSOVE SUNOLE S i ON UCSP
- \'
5 400 's o. m- < =r- - r-ry s' 5
)9 l
I I
! - FLU 10 TEMP.
a t - 5RT. TEMP . RT TCP GF U.P. ' 3 350 (, ' c' i I l l *
! SOCREC l I i 0 50 100 150 200 TIME AFTEM SREAK (5)
Fig. 3-3 Fluid te=peratures in upper plenum i 1 l 1
JAERI-M 84 -221 o g r M u fte etait . ./P sca:ss fte e.. art BOCREC 50CRE: ass : 13 .ss t-: f!57 St-SM3 rgg; $3 5*3 ' agavt Sum 0LE I 450vt SUNOLE 5
. 4 l
, 425 I
/ ( * - :.5 - . 25, 3 -- I
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f!Pt 8Ffte Sagan ts: gg.g agtgg gegen agi osa I3 '453 13 fEst St-SM3 ff37 St-SM3 ABCV! SUNOLE 2 880VE SUNOLE $ .,4s a- - - L 38 .4:s - - -- -
- .s -
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. 2.,- .n - . - - . . . .- ... -
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- 178 ' - -- - - -
150 3 g, sa 7s icd'8 "N n so 7s i:i'"8 f tpg eerge gegen s 33 fler estre sete= tst - 450 '*8 '83 "* l0 ft$f $1-SM3 fEST $1 SMS
< ag3VE SUNCLE 4 ASQVC $UNC([ $
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i f > l ss o a sa n icd'8 "8: n sa :s .:5 8 8 ftpg safgg getes ist f!"g safge gegns rg Fig. 3-9 Co=parisons of fluid te=peratures just below end' box cie place and differential pressures across end box tie place over 3 bundles in Test SI-SE3 JAERI .\t 84 - 221
+ e/, acmdss ! t rtatt e
s et-e.tat.1 g0u tre etAtt SCCREC SOCREC
- i.3 .so I g.3 es3 TEST 51-!... T!!? $1 594 h agavt sywctg $
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-. y 3.s _
2 :_ . s% jLa .-.Th.f. b
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.- 0.8 .
_A - ._ g % W _' . _ 400 - 33g 403 - - - - - - - - - ~ < - _ 3.0g
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25 54 ftpg a#?tt Bet ** ill ft=t satte ast4N 135 Tig. 3-10 Cc=parisons of fluid ce=peratures just below end box cie place and differencial pressures a~ cross and box cia place over 8 bundles in Test S t-SF.4 JAERI-M 84 - 221 1 00 -- z-_ ~ 0.75 j- -' i _ ~ '
. i z < ~
S : i C 0.50 ._ i . c _ 1 n l [ . S : ! TEST S1-SH4 : l ? 0 25 ELEV 3 35-3.68S M
~
O BUNDLE 2 -
~
A SUNOLE 4
+ BUNDLE 8 0.00 50 75 100 0 25 TIME RFTER BRERK (5) 1 00 ' =_ xm e . \
7 0 75
,%^q z
S : i I C 0 50 > e . . I S - 4 TEST S1-SH3 . 5 0 25 ELEV . 3 36-3 685 M - O BUNDLE 2 :
. A BUNDLE 4 - + BUNDLE 8 ~
I 0 00 25 50 75 100 0 TIME RFTER BRERK (S) Fig. 3-11 Void fractions in Bundles 2, 4 and 8 at upper part of core
~ _ . _ . . _ _ , . _ _ _ _ _ _ . . . _ , _ . . _ _ ._. _ _ , . - _ , . _ _ _ _ _ . . - _ - _
JAERI .\184 -221 10 i , SETWEEN SUNOLES S-S ELEV. 1 905 M . ISMCCIMEC CURVE 1 l I
- 3.5 __ . e ;,3g,~
r Break valves c:en ___ 7 ggt 51-5H
=
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n ; p , [ E i 5 30CREC l l-c .0 5
, 1 -1 0 0 100 200 300 400 SCO 500 f!ME ($1 10 , ,
SETWEEN SUNCLES S-S ELEV. 3.235 M (SM00THED CURVEI 05 3reak valves open d
= , - TEST 5!-5H5 j - i -- TEST 5 -5H4 4 i , - , n -
4j'p6. ,e
= c.
h,\pf'fr%%,pp.-d 2 c -0.5
- ,4 t! ! , i SCCREC ,
I l
' f, l ! , i ,
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'I* 500 0 100 200 300 400 500 TI-E (51 -
1.0 ' 4
. SETWEEN SUNOLES S-S I i SELOW ENC S0X IIE PLATE
., l ! (SMCCTHED CURVEl
. 05 , -h -
TEST St-5H5 E Break valves open -- TES T 51-SM4 e x '
- t , t I
w z g,g sg1....,_.'...._.. y . l [Nl' t 'C.,'% I p %;'s&M a t , ,, -.
- p. i >'"*DV i {
c .3 e . t BCCRfC i l' ; i i l
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7ts! (51 Fig. 3-12 'orizontal d differential pressures becseen Sundles 3 and S JAERI-M 84 - 221 15 . , i l . g,g _ Break valves ocen f li f 4 It a
= a t i !,
- s. ,, 5 ,
.. . t!. VJ f !,I '__ ' .. , . ,, A#k -a s.~-
g.g r n
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iV !* i l , O I BOCREC 3 i 2-0.5 : l BETWEEN SUNCLES 1 - 1 ELEV. 1 90S M tSM00THED CURVE 1 ;
-I*O l - TEST St-SH3 - TEST SI-5H4 e s O 100 200 300 400 500 500 TIME (53 15 I I SETWEEN SUNOLES 1.-S Break valves open ELEV. 3 23S M --
t.0 -- tSM00THED CURVE 1
- ' - TEST S!-SH3 e r. - TEST St-5M4 g05 t
_ t' t - g ,h !n!d. p_-_ -- -- A g , , i
. g - pl ,,, n.l1yv a 4 8
e ,* tm
;g-0 =. . , I&;, , r v p' = ; -1 0
[s_ SOCREC i: , i
-1.5 0 lh I 100 200 300 400 500 500 TIME (51 15- , . .
SETWEEN SUNDLES 1-0
!! LOW END 80X T!E PLATE-t.0 , , , (SM00THED CURVE 1 - l Break valves open~ - TEST st-5H3 E05 5
V t - TEsf st-sH4 w - e 0.0 k~ E-0.5 A; .c s , ,,v , j N %1 i g 30CREC l
-1 0 di' f, .t.5 600 0 100 200 -300 400 500 TIME 151 Fig. 3-13 Horizontal differencial p.~essures between Sundles 1 and 8 43 -
1: JAERI-M 84 - 221 FALL BACK FLOW RATE CALCULATED FROM CCFL CORRELATION
- TEST SI-SH3 -- TEST SI-SH4 20 -
l
- : /vg l Q gg* :b /S \
c3 g isj l i k
\
ill
\ . - I I I \
Il wi - y ' c e'l .I l c 10 . y
/ . ',j,! j i = -ig,i f.J c I II ,f d i o \ l ^ ~
4 l \
.; 5 , ., g c . ; , . "- . / \
g
'/ \ ' " I/g,I 80 Cat: \ ; ~
O 150 0 50 100 Tine RFTER BRERK (S1 Fig. 3-14 Esci= aced fall back mass flow ra:es vi:n CCTL correlacion COLLAPSED LICUID LEVEL IN UPPER PLENUM ABOVE'BUNOLE 4
- TEST S t-SH3 -- TEST SI-SH4 i 15 E ,, I -
6 .
- /I il J I,V t 6 (i
l ' . c 10 d \ i
.a - i i l !' .
t W I b i r I q > t
" I I r
4 -
; f I C
I l l
~
50.5 I/
?
l 1
, I l I !
J I i i i tc xt:
-l 'g
- j
\ -/ I , ,,,, - ~ ~ --] \,;_,,,_,,,--y _
l 00 50 100 150 0 TIME AFTER BREAK ($1 Fig. 3-15 Liquid levels in upper plenus
JAERI-M 84 -221 CDRE FULL HEIGHT DIFFERENTIAL PRESSURE BUNDLE 4 O TEST SI-SH3 A TEST S1-SH4 2S ,
- ( i socat: -+
]L ., }l l // ' ! , i 0 100 ~
200 300 400 ~ TIriE RFTER BRERK (S1 F ig . 3- 16 Ver:ical differen:ial pressures across core full height 6 9 45 -
JAER!-M 84 -231
' CLEv. 3 30-3 885 M ELEv. 1 365-1 9CS M SumCLE 4 $UNOLE 4 -.T f st-sMs - f ts? st-sMs -t T st-sMe - f tsf s!*sMe 1 Co 1 '" . ,....,- j ,
v..,*,e s, S . , , , , , , , , . - g,95 #, g, -- _ . -
- o.ts - - - - -
1 ,. I -
! . h.'i f 2 .
o.so ,; ' , go.so --- - 5
*i ! : =
t t
! l l I !
3a.as -- 2c.rs -- I- . i l i i l . o.oc tso too 8*88 too o so too 0 so too 150 fi g w ita estas ts: fts wfte sata = is ELEv. 2 895-3 235 M ELEY. 0.7-1 24 M Sum 0LE 4 SumCLE 4
- itsf st-$ns itsf st.SMs - TElf st-5M4 - Test st.sna 1 on w: , ,..
s
= - , . _
t no -
\m.*%% - c.7s fly -- '~ - - e.is + - - - = '%*},-- - - -
I . E ga.so
- - - - - - - -+ --
Ge.so
- i
! l I E . !
3a.as - - - - E o. s - - - - - - - - - - ~
; 4 e
8 "" o so too tso too 8'88 so :o iso aco o f!w witz ent*4 t al ftp.t wfte sete= ts: ELEY. 2 03-2 57 a. ELEY 0.C95-0 575 "I SUNOLE 4 SumCLE 4 _f f .gws = itsf st sMs f f - S.e+ " ftsf sl*888 1 00 y,, - - _ t.no -
i,,/ ' '----------. - ; j I i .,g,9g . ... . - o.7s ,
1 - I i g
- 5. I
\t. ,
o.se -* -- -- - :" 8 *88 ' s gg,gg l8*8*
! % _ ' ,,_,p. . a -
I
><x .f.
i o.ot so i
, ,a a so too iso aco o
it., wfe os i., in zoo ftnt wfte gaten ist Fig. 3-17 Void frac:Lons in core at six elevations g-
BOCREC 80CREC IEST SI-SH3 TEST St-Ig TEST $1-SH4 4 1 . 2.0 . . . . . . . . .
~
1.5 --- ; - - - = -
-- - ---'=--
d N 5
.i, j 1.0 ;
" 6 TEST SI-Sil3
' A TEST SI-Sil4 7 o I + TEST S1-19 :
o -
)
a 0.5 3 00TTOM OF CORE BARREL 0.0 150 0 50 100 TIME OFTER BREAK (S) Fig. 3-18 Lisguid levels in lower plenum
JAERI-M 84,-221 0.50 .
- TEST SI-SH3 0 25 E / e ?^" = 0 00 b
h(f f -- U S
-0.25 , ) +- 80CREC -0 50 0 50 100 150 TIME RPTER 3RERM t31 1
0 50 , n - TEST St-3H4 0.25 I O 0 00 ,
, NM ' - != < , /
h
-0 .25 g , y\ 680CREC -0.80 50 100 150 0
T!rit RFTER BRERM ($1 I 0 50 l - TEST S1-19 pmq 0.25 l 5 e a ca q>v A [~ 8
-0 25 1h t- 80CREC -0 50 50 100 150 0
TIME RFTEM BREAK (31 Fig. 3-19 Fluid velocities below core barrel _g_
JAERI-M 84 -221 - 20
- Test st-sH4 Fall back water flow rate 15 '1 10 I Beginning of
- ' ' bottom reflood 5 '-
O' ' ' ' ' ' ' ' ' ' 0 50 100 150 7 10 D : TEST s!-sH4 SteCm generation rate E - 5 - [0 o 0 50 10 0 150
= 20 -
g - rest st-sH4 Penetration water flow rate 3 15
' 'PE' E ' " '0
[ 10
- (
5 - 0'O ' ' 50 100 150 Time after break valves open (sec) Fig. 3-20 Esti=ated pene::ation water flow ra:e from upper plenum to lower plenus in Tes: $1-SH4 '? 1.2 TEST SI-SH4 t.0 - p
; Void fraction in 0.8 -
broken cold leg . C pressure vessel side 3O y 0.6 - g
~
32 $ x 8 9 0.4 - i
\% ;
2 i i3
~
0.2 - Beginning of bottom reflood 0 ' ' 150 0 50 100 Time after break valves open (sec) Fig. 3-21 Voi.I fr.setion in broken cold leg pressure vessel side in Test S I-Sil4 9 a
JAER!-M 84 - 221 . 15 '
~ l _
LOWER PLENUM FLASHING RATE ~ TEST SI-SH3 _ E - e x10 Y . c- :
= .
g - BOCREC t ; E05 us , - 5 u
- h f g ppW:%~"
00,100 0 100 200 300 400
. TIME AFTER BREAK !S) 15 , , ~
LOWER PLENUM FLASHING RATE TEST S1-SH4 E - e t x10 -
. l !
l U . l l l c:
~
1 E P BOCREC e . 2 205 ; g g . _a ~ A i : I 00
' 'l
- dA' l
-100 0 100 200 300 400 TIME AFTER BREAK (S)
Fig. 3-22 Flashing rates in lower plenu:n mi r g d" O S I
,i - r e
m 00 )S
- o
( c 1 n w K o 34 d tl ii A SS E i n tt R SS B s
. C l Jf, t II e l . H C SS R v A l . 0 EE ' E e . . a l I II T
l R r F d E i O u M . i q O E L C oM N SI 3 T 2 H - 3 0 34 . 0 HH9 g SS1 i N IIl g g
' F I
SSS - Ct E S L TTT . R C I E SSS 0T 8S V EEE E ' E TTT . T L OA+ - o D 0 I 4 2' 8 U JW wJ. Q ;5a e J_ - Q I L I i
JAERI-M 84 -201 20 - , , , MASS FLOW RATE IN HOT LEG TEST S1-SH3 -
~ ' ~
O REGION 1
- A REGION 2 E + REGION 3 o 10 . X REGION 4 -
5 -
' ~
x ! ! l m
.,M 9 i. - .. - -Y bC h3_7_- .i 4 ^
E, / !. l _ r . i l ;
- . l _
. l -10 400 500 0 ^1ba 200 300 SOCREC TIME'AFTER BRERK (S1 20 , - MASS FLOW RATE IN HOT LEG i - TEST S1-SH4 1 -
O REGION 1 l
- A REGION 2 -
m l + REGION 3 A A A g -}I{I L x REGION 4 vaf \ f l f h jy *
-~s{jk; = l k
l 0 200 300 400 500 fl00 TIME RFTER BREAK (S1 80CREC Tig. 3-24 Mass flow ratas in four regions of hot leg L
y-JAERI-M 84 -221 4 12
- VOID FRACTION IN HOT LEG ! :
TEST S1-SH3 - E10 . 3,_ : 2: O, 1 0 1 _ 5, ~ E08 . ( 5 -
! i i
i . i ' ' 506 - x g : : E '4 j C h O REGION 1 I : l ; o A REGION 2 '
>02 - - + REGION 3 i I
- l X REGION 4 l :
\
O ^100 200 300 400 500 TIME AFTER BRERK (S1 SOCREC 12
- VOID FRRCTION IN HOT LEG i :
- TEST S1-SH4 ', :
g10
) ,y 7 0 0 C -
50.8 ,;t [ z a
) - } ~
1 5 O(.'s j : l \f g - t, ; X : g 0.4 ----- y\ . C - X 0 REGION 1 l' ! E J I A REGION 2 I
> 0.2
_I + REGION 3 X REGION 4 i V: _ 00 - 1 M m o A "500 0 ^100 200 300 " 4d'0 TIME RFTER BRERK (S} 80CREC Tig. 3-25 7oid frac: ions in four regions of hot leg STERM OUTFLOW RATE ICL'. STERM FLOW RATE + BCL. S/W SIDE STERM FLOW RATE
- FLASHING RATE IN S/W SEPARATOR O TEST SI-Sil3 A TEST SI-Sil4 8 . . . . . . . . . . . ....
(---80CREC
*6 -
E y
" m W
4
~ ~ - - , tu '" ~ % e E M i O 2 -
e z
% N T a WD m -2 O 100 200 300 400 TIME OFTER BREAK (S)
Fig. 3-26 Steam outflow rate tlirougli tiot leg
JAERI-M 84 -221 STEAM GENERATION RATE IN CORE BY HEAT SALANCE
-- TEST SI-SH3 --- T E S T S t -S H 4 S
l
- 1 O t s
e 5 j ,e' s ,...s ~* m
,/ - ~4 -- ~.,'
2 ./ , e. _ ,i, E /t - a s
! /
t w i I / 2 - ' e / , w > I s
-..i /
4 e2 ..w I \- . Y; l l E .) ' L_ s ' ' l w 5
+- SOCREC 0
0 SO 100 150 200 TIME AFTER BREAK (S) . Fig. 3-27 5:4a= genera:ica ra:es ebcained f ra hea balance :alcula:ica TOTAL STEAM GENERATION RATE HEAT SALANCE + L.P. FLASHING
- TEST SI-SH3 -- TEST SI-SH4 6 ,
i l t e s x
, ~ % ,---
4,s, i 4 _ _ _ _ _ _ . ... . _ _. _ ._ f z e r
/ - -v, ,
m e l a g / C g / E ' i' /
\ / $2 y 'z v'pd -
E bk../ w .
- 4- BOCREC 0
0 S 0. 100 ISO 200 TIME AFTER BREAK (S) Fig. 3-23_ Total s:aam generacica rates obcained fres heat balance and lower plenus flas. ting
CONDENSATION RATE IN UPPER PLENUM O U.P. INJ. RATE = CP = SUBC00L / HFG A STERN DENERATION RATE - STERN OUTFLOW RATE 4 . . . . . ... . . . . . . . . o u) N
@3 E :o I E I z 2 r a
j L 1 g% vw _ OMe. Z o u
' l ' ' ' ' ' ' ' ' '
0 O KiOO 200 300 400 TINE RFTER BREAK (S) 80CREC Fig. 3-29 Steam condensation rate in upper plenum in Test S I-Sil4
JAERI-M 84 - 221 i 1300 , , BUNOLE 4 / CENTER RCD ELEV. 3 19 M
~ $ 4 30CREC ~ {g![ ll:!M 5C0 y b ' '
a 700 , % ,
/ '"'I-
, j %-d ,' I l E / E 500 l l r4 l l 6/ j ;I L I . O 100 200 300 400 500 TIME AFTER SREAK ($1 1300 , , SUNOLE 4 / CENTER RCD ELEV. 1 905 M
; 1100 , - TEST 51-5H3 M. - TEST 51-5H4 a' l N! j l 5
900 3 8 ' N,\g .
" 700 = 'A a
E 500 -
,_. . I l , 0 100 200 300 400 500 TIME AFTER BREAK ($1 1300 , ,
SUNOLE 4 / CENTER RCO ! ELEV. 0 95 M
~
g 1100 - f!ST SI-SH3 , . --- T E S T 51 -S H 4 e' 900 p/ g-s l l E \
- 700 -
5 m E 500 l i I l 300 0 100 200 300 400 500 TIME AFTER GREAK (SI
-Fig. 3-30 Heater red surface cammeratures at elevacions of 3.19, 1,905 and'O.95 m L-
r JAERI-M 84 -221
+ Test St-SH3 Test SI-SH4 00 ^ \
L
- Elevation 2.76 m j '
- 800 1200 1100 - ,1000 .s c " ~
8 Elevation 1.735m . 5900'
# 900 7 ,
800 7 dNg ' - 700' I Elevation 0.52 m' ' V'
! 2 3 4 5 6 7 8 Sundle No.
Fig. 3-31 Hori: ental dis::ibutions of turnaround tenperatures a: eleva:icas of 2.76, 1.735 and o.52 s 4, , . . . . I " X 3 Sundle4 e : Center rods
/
2
= . .S -
i E ' ~
- O $1-SH3(Comtaned inilSct.) _
w I l l / A SI-SH4 (C:mbined ini./Sub.) 0
~ *// ' ' 'xSI- 19 (Ccid leg ' ini.) - -10 0 0 100 20 0 300 400 500 Time after 80CREC (SeC)
Fig. 3-32 Quench envelopes in 3undle 4
b_4;7 u-0 0 5 0 i [* ,' 0 4 d - f o i 9\ 1 t ol fo n ge r 0 0 3 S inn m - t o 0 i s igl l e e o ' 0 T Bb 2 0 7 8 i
' 0 1
s e e - e
=
ld l l d i. - l l}, j: I- - _ I ~ I I l y l 1 i. l I ; d n n - .l- : : - ~ - - : n u u 4 3 2
;.~.0 . ) u B B i
0 c b 0 e l
- 0 s l o
- 5 ( a
- n i
d 0 n 5 6 i f o 0 e s ol o ' p e f 4 o p l e le g er - o d d 4 n s l n n e u u i S l i inn m i o ' 0 0 e v v n . B D - gt t 3 l o e I / e o - v h o o S / Bb c 0 k n i t s ' 0 a e e 2 u T - e r q 3 4 - b f 0 o _ le e s '- -
' 0 d d l
i l l I
- 1 r n n
I 1 g l 1 l I I 1ll } I; ' e o u n u - f t i s B D o r
.. - - - [- - . { - .: ._:;.: a + - 4 3 2 0 e p
g 0 m 0 m o
- 0 C 5 iT 3 I 2 -
3 e d 0 3 le l i o ' 0 ol o f d d 4 n u n f g u gr e - i D B , n 0 F nm i i 3 ' 0 o
- H i n o 3 S gt t I
- eo Bb S 0 ' 0 t
s 2 e - T -
- 0 i
il I I l ! l I 1 I I l l lg 0 1 l I '
, - [- .
- _[ - - - : - ~ - - : ~_. '
4 3 0 2 g O E# II8c - o E 9. j goa c9._9a w
, 8i
JAER!-M 84 - 221
-o-- Test S1 - SH 3 --o- Test SI- SH4 -x- Test St - 19 Elev. 2.76 m ~~ '
g400 f 7 x 4 7 . p+g /i, ,eV9y^, f A ip' 2 - 4 A c . 4 - - tre \,
- 8. 3' ' 'g E i, \
' ' '- I 300 ' .a e 'a' h,-
i 9 . Elev. 1.735 m i a 300 - - -
$ i%A ! % ' **g#*^ P M (4 g $e zoo W ~~ Y - ._E_ -5 5 =
0 200 Elev 095 m . h 100 h "px"px. Nx *--my.-x- g 1 2 3 4 5 6 7 8 Bundle Number Fig. 3-34 Radia!. distributions of quench times at elevatices of 2. 76, 1.735 and 0.95 m JAERI-M 84 -221 r 8 8 8 8 8 g g g Downcomer O O O O = O O O O 0 O O O O (0 0 0 y 1 2 3 4 5 6 7 8 Cold leg Elevation 2.76 m
--o--- Test SI- SH3 } : Cold leg side --6-- Test S I- SH4 -x- Test SI- 19 S: Opposite side 0 l 4 40 i0 t0 t4 i 0 i 6 t > Q { } _
g Y I I I d l l1 $ 0 lg 6 ;, gg a* 300 - 1 I i i 1 I j \
\ l I l g I )
j ~ l I l t 5 1-g' I I
\
o
\l Ii
= - n \ ,i ! \i'l i 'l 2 ~ l I l I
= 200 - I j' i [
i i 8
~
I I l I d I e I
~
I 1
=
E - l r l I l l l " = 100 -o i I k si d i ' jg --l /\ g l I I l g i i I O g I l f b LY a O 'l 0 t 2 3 4 5 6 7 8 Bundle Number
~ig. 3-35 A:i=u:hal dis::ibutions of quench ti=es a: eleva: ion of 2.76 m
l l
'JAERI-M S4 -221 Elevation = 3.19 m O No quench before 80CREC A Quench before 80CREC and dry out again
- Quench before 80CREC S 1-SH 3 ( Saturated water injection into U.P. )
< Injection side >
1 1 1 1 i l i 1 8 : : : : : 3 O O OC O O 0C O O OC O O OC O O OC O O 0C #0Ge # 0 et o . o a a # . o 1 i i i i i i i radial
< Extraction side) - --
SI-SH4 (Subcooled water injection into U.P. ) azimuthal (Injection side > I l l l l i l l
- : : 1 : I :
l D G A SC O O OC A C Ae O A AC O O OC OOOC A C AC 0004 l l e e A e e o e o h h
< Extraction side >
I 2 3 4 5 6 7 8 l l Bundle No. Fig. 3-36 Horizon:a1 dis:ributions of early quenched rods a: elevation of 3.19 m in Tests Tes:s 31 -5H3 and S ?-SHl.
' BUNDLE 4 ELEV 2.33 M (SM00 tiled CURVE 1 (9 TEST SI-Sil3 A TEST SI-Sil4 + TEST S1-19 400 . . . . . . . . . . . . . . .= ..=.~
x w N E 300 E $
% m X " ~
I - E 2 ; 200 % I 1J _ i O LJ
^-
f' $
, 100 -- -
E i f_", M s 0
- 80CREC for Test 51-19 H g E I BOCRfC for Tests 51-5113 and 51-5114 'S " ' ' ' ' ' ' ' ' ' ' ' ' ' ' ' ' ' ' ' ' ' ' -100 300 400 500 O 100 200 TINE AFTER BREAK (S)
Fig. 3-37 Ilea t transfer coefficients at 2.33 m in Bundle 4 {
S 300 , , , ,. 300 , , , , Elev.. 2.76 m . - Elev. l.905 m g - Bundle 4/ center rod Y ~
.j li; . ~
Test SI-SH3
---- Test St-SH4 )-
7 200 \
- 200 ( .--- Test Si- 19 :
g .g .. . \
.e .9 -\. -- i, \ $ \ 'g ~ \ -N, _ _
, N. g \. ., 2' 100 - N . .s ,- E 100 -
% .s._- -- , ~,
n ,,, s e e .\.s~~ . N -
,.X, .N ~ ,..s.. s%-~. s y 'g, s
g. g j
''''''''''''''' 0 " '''''''''''''''''*
0 2.0 2.5 0.0 0.5 1.0 1.5 2.0 2.5 00 0.5 1.0 1.5 -. m Distance from quench front Im) Disionce from quench Ironi (mI B I 300 300 K 8: , , , , . . . .
=
l Elev. 1.38 m g Elev. 2.33 m g 7 i l3 i \ ~ m' 1 S.' [ 20e \. y 200
.s -\
5 s= .\-\ a
% ,NNN. -
8 \ E \\ '
;,, 'N' N g i '\.
s* -\ E lh0 - E 100 - e \ ~ .- . _ '
- s e 1 gs % \. ._.. s N. u.
s
- u. ,
\, E
- 1 g ga a 1 a a a i a a a 9 a 1 .
0 ' ' ' ' ' ' ' ' '' 00_0 0.5 1.0 15 20 2.5 00 05 1 .'0 1 .'5 20 25 l Disionce from quench froni (m) Distance from quench front (m) Fig. 3-38 Ileat transfer coef ficients vs. distance f rom iguench f ront at elevations of 2.76, 2.33, 1.905 and 1.38 m in Bundle 4 4 9
JAERI-M 84 -221 o o N N E
. E .
O .m O
. NZ rn N S s - : .-
s -( i - m s g =
=
2 i a 2 - w hl . O k w - C.
~
w I[. . . 5 o
} . / #.
- g c
g'/s p' . U r e f/ a
. i . O. E . . O 5 es *' - 5 s' . /}- . w C
s //
~
0 g .' s .
~
j . c-3 /! r/ c -l: - v
, '/- ,s'j ~
l O* ~ " O .-Q E}
' o a s - . ,' ! = /. - . = / - s' .
5 ~ s' / , O f. j . . O .* a w tn N - 00 w rn N - 00 0 ~ 6 6 6 6 6 6 6 6 6 6 u ? '
?
(D-( ) U01100J} JG10M (L.l} U0tt00J} J410M E w ~2 m : O C -* 3
'y. N /
f N ~# a e C
- a. _
./ > e.
1 ~ (/ . e rn w l
.j' . ON l .E =zm i 1 o- - E I ij m e mm- I N ro i.
m.
.E rn -
u swi== == i
= o l 1
I \ g
. u N 2MMM / [. .
g ,1 . ! 2 . 3 3 ' $ I i
. a m ,$$}~44 ' I'
- e. e I
.O ,i g
u w n I . . a l. i
- l ;
5 a2 e p .
. I -
y
/
i .I : O.
== -
l .
/ ! l . Os == ?
g
./
1 j I I e i . t - u .
- 0 1
/-/
g i i
~
y -I .b %
/ .
3 f m
/ l D '5 . / l C & !. / .
O / / . O
/ l . / ! . ! - s / . .l -
O s' j,/ -
, /, /.. , , , ,a .
O T rn N - .& w sn N - CO d 6 6 6 6 6 6 6 6 6 (D-I) 00tt0CJ) J8tDM (D - ( ) U0tt0DJ} J310M JAER!-M 84 - 221 w T o - o m ~, m ., 6_ ,, g er = i o
- e. . . , . . -s. i. - -
N. . \i . g i.
- n. oc A y _?
o.e . _ .d i og .J i. .
= = '., . ".
a s s.\. - 5 ('s, -
~
m
= .=.,,
sn 1, - ss , g5 -R a
'm' N s - -
23 g n _ w -
. N _ . -E s
_a - w w = w - o
, , o ,- . 3 -
oo o oo n - 8
~ 8_ 2 8 a
a (M P/m) ;usp!;poo Jaisuo;; teaH (M p/m) jusp!;;aos Ja;suo;; ioaH hA - a c -"J T T. "J
-=
o . o -
.U. c - - % e =>
m, ae me v , o.. t o i mm s
- = c m g
g s . .= % .
- t .
S g - c 3 N
- s. -
_h -**'- . . s s, _
.2 .e ~;
. ~ _ ug oJ
\
un oo -
\ a m 3mw -_ 't i
r,
~
g n y% y a m, ,- ~ 2 i o - _y
-E _i _ _i ,_ y a
g oee ', a- - " N D ?,1 j ' s d M w
'sN s, -
g -r
~..-,, -s m , - s ~
w : .i u o R , , o E g g C# g oC
~ _
(y.gu/m) rJsp:;;aco Ja;suo ; toaH (3.pn/m) ; cap!;;aos Ja;suo;; seas . JAERI-M 84 -221 Appendix A Slab Core Test Facility (SCTF) Core-I A.1 Test Facility The Slab Core Test Facility was designed under the following design phylosophy and design criteria:
- a. Design Philosophy (1) The facility'should provide the capability to study the two-dimensional, thermohydraulic behavior and core flow within the reactor vessel especially due to the radial power distribution during the end of blevdown, refill and reflood phases of a simulated LOCA for a pressurized water reactor.
(2) To properly simulate the core heat transfer and hydrodynamics, a special emphasis is put on the proper simulation of the components in the pressure vessel. As the components in the pressure vessels are provided a simulated core, downcomer, core baffle region, lover plenum, upper plenum and upper head. On the other hand, si=plified primary ' coolant loops are_provided. As the pri=ary coolant loops , are provided a hot leg, an intact cold leg, btoken cold legs and a steam vater separator. The object of the steam / water separator is to measure the flow race of carryover water coming out of the upper plenum.
- b. Design Criteria (1) The reference reactor for simulation to the SCTF is the Trojan reactor in the United States which is a four loop 3300 MWt PWR.
The coi reactor in Japan is also referred which is of the similar type to the Trojan reactor. (2) A full scale radial and axial section of a pressuriaed water reactor is provided as a simulated core of the SCTF vich single bundle width. (3) The simulated core consists of 8 bundles arranged in a row. Each bundle has electrically heated rods simulating fuel rods and non-heated rod with 16 x 16 array.
.(4) The flow area and-fluid volume of components are scaled down based jon the core flow area scaling.
(5) To' properly simulate the flow behavior of carryover water and entrainment, the elevations of hot leg and cold legs are designed to be the same as-the PWRs as much as possible. (6) The honeycomb structure is used as the side valls which accomodate the slab core, upper plenum and the upper part of lower-plenum, so _g_
JAERI-M 84 - 221 as to minimize the effect of walls on the disturbance of .the core heat transfer and hydrodynamics. (7) To investigate the effect of flow resistance in the primary loops are provided the orifices of which dimension is changeable. (S) The maximum allowable temperature of the simulated fuel rods is 1900*C and the maximum allowable pressure of the facility is 6 kg/cm absolute. (9) The facility is equipped with a hot leg equivalent to fo,ur actual hot legs connecting the upper plenum and the steam vater separator, an intact cold leg equivalent to three actual intact cold legs connecting the steam water separator and the downcomer and two broken cold legs, one is for the steam water separator side and the other for the pressure vessel side. (10) The ECCS consists of an Acc., a L?CI and a combined injection systems. (11) ECC vater injection ports are the cold leg, hot leg, upper plenum, downcomer, lover plenum.and above the upper core support place. These portions are to be chosen according to the object of the test. (12) For better simulation of lower plenum flow resistance, simulated - fuel rods do not penetrate through the bottom plate of the lower plenum but terminate below the bottom of the core. (13) For measurements in the pressure vessel including core measurements, the feature of the slab geometry of the pressure vessel is utilized as much as possible. Design and arrangement of the instruments are done so as to be able to carry out installation calibration and removal of the instruments. (14) View windows are provided where flow pattern recognition is important. The locations are,.the interface between the core and the upper plenum, hot leg, pressure vessel side broken cold leg and the down-comer.
-(15) The blocked bundi'e. test is carried out in Core-I in order to investi-gate the effect of the balleoned fuel rods and the unblocked normal bundle test for the Core-II and -III.
(16) Simulated types of break are cold leg break and hot leg break. (17) The components and systems such as the containment tanks and ECC , water supply system in the CCrF are shared with the SCTF to the
. maximum extent.
The overall schematic diagram of the SCTF is shown in Fig.A-1. The principal dimensions of the facility is shown in Table A-1, and the
1 JAER!-M S4 -221 comparison of dimensions between the SCTF and the referred PWR is shown l in Fig.A-2. l A.l.1 Pressure Vessel and Internals The pressure vessel is of slab geometry as shown in Fig.A-3. The height of the components in the pressure vessel is almost the same as the reference reactor's, and the flos area and the fluid volume of each l component are scaled down based on the nominal core flow area scaling. The core consists of 8 bundles in a row and each bundles include
- simulated fuel rods and non-heated rods with 16=16 array. The core arrangement for the SCTF Core-I is shown in Fig.A-4, which includes 6 normal bundles and 2 blocked bundles. The core is enveloped by the honeycomb thermal insulator which is attached on the barrel.
The downcomer is located at one end of the pressure vessel which corresponds to the periphery of the actual reactor. The core baffle region is, on the other hand,. located between the core and the downcomer. For better understanding, the cross section of the pressure vessel at the _ elevation of midplane of the core is shown in Fig.A-5. The design of upper plenum internals is based on that of the new i Westinghouse 17 x'17 array fuel. assemblies. The internals consis't of control rod guide tubes, support columns, orifice places and open holes and those arrangements is shown in Fig.A-6. The radius of each internal i is scaled down by factor S/15 from that of an actual reactor. Flow re-sistance. baffles are inserted into the guide tubes. The elevation and I ! .the configuration of baf fles plates are shown in Fig.A-7 and A-8. . The height of the hot leg and cold legs are designed as close to
.the actual PWR,as possible. However, in order co avoid the interference of the nozzles in the dcuncomer, the height of nozzles for the broken cold leg and the intact cold leg are shifted down compared to that of the hot leg as.shown in Fig.A-3.
A.l.2 Heater Rod Assembly The heater rod assembly for the SCTT Core-1 consists of 8 bundles
. arranged in a row. These bundles are corposed of 6 normal unblocked - bundles which are located at the 1st, 2nd and 5th to 8th bundles and 2 blocked bundles which are 3rd and 4th bundles as shown in Fig.A-4 .Each bundle has 234 electrically heated reds and 22 non-heated rods.
The dimensions of the heater rods are based on a 15 = 15 fuel rod bundle. JAERI-M 84 -221 and the heated length and the outer diameter of each heater rod are 3.66 m and 10.7 mm,'respectively. A heater rod consists of a nichrome heater element, magnesium oxide (Mgo) and Nichrofer-7216 sheath (equialent to Inconel 600). The sheath wall thickness is about 1.0 mm and is thicker than the actual fuel cladding because of the requirements for thermocouple installation. The heating element is a helical coil and has a 17 step chopped cosine axial power profile as shown in Fig.A-9. The peaking factor is 1.4 Non2 h eated rods art either stainless steel pipes or solid rods of 13.8 mm 0.D. The heater rods and non-heated rods are fixed at the top of the core allowing the rods to move downward when the thermal expansion
~
occurs. In Fig.A-10 the axial position where blockage sleeves for simulat-ing the balooned fuel rod.are equipped is shown. The blockage sleeves consist of three types of sleeve, one is used for the rods at the corner
~
adjacent to the next blocked bundle, another for the rods adjacent to the side walls and the third for the rods except for the periphery of the blocked bundle. These are named A, 3 and C respectively in the Fig.A-ll and these configurations for these are shown in Fig.A-12. . For better simulation for flow resistance in the lower plenum the simulated rods do not penetrate through the bottom plate of the lower plenum as shown in Fig.A-10. A.1.3 Primary 1. cops and ECCS. Primary loops consist of a hot leg equivalent to the four actual hot legs, a steam / water separator for measuring the flo'w rate of carry over water, an intact cold leg equivalent to the three actual intact loops, a broken cold leg on the pressure vessel-side and a broken cold leg on the steam water separator side. These two broken cold legs are connected to two contain- ' ment tanks through break valves, respectively. The arrangement of the primary loops is shown-in Fig.A-13. The flow area of each loop is scaled down based on the core flow area' scaling. It should be emphasized'that the cross section of the hot leg is a elongated circle to realize the proper flow pattern in the het leg. The steam / water separ.ator has a steam generator inlet plenus simulator to realize the flow characteristics of-carryover water.- The cro'ss section of the hot leg and.the configuration of the steam generator. inlet-plenus simulator are shown in Fig.A-14 L A pump simulator.and a loop _ seal ~part are provided for the intact l cold _' leg. The arrangement of the intact cold leg is shown in Fig.A-15.
.i
LAERI-M 84 - 221 The pump simulator consists of the casing and duct simulators and an orifice place as shown in Fig.A-16. The loop resistance is adjusted with the orifice plate. In principle, ECCS censists of an accumulator and a low pressure injection system. The injection port is located as already described in the design criteria. Besides, the UCSP extraction system is provided and the UCSP water injection and extraction systems will be used for combined injection tests. A.l.4 Containment Tanks and Auxiliary System Two containment tanks are provided to the SCTF. The containment
' cank-I is connected with the downcomer through the pressure vessel side broken cold leg and the containment tank-II is connected with the steam /
water separator through the steam / water separator side broken cold leg. Especially in the containment tank-I, carryover water f rom. the downcomer is =easured by phase separation. These containment tanks and auxiliary system such as a pressuri:er for injecting water f rom the Acc. tank, etc. ~ are shared with the CCTF. A.2 Instrumentation The instrumentation in the SCTF has been provided both by JAERI and USNRC. The JAERI-provided instrumentation includes the =easurement of ta=peratures, pressures, differencial pressures, liquid levels, flow L velocities, and heating powers. USh*RC has provided film probes, impedance proces, string probes, liquid level det'ectors (LLLs), fluid distribution l -grids (FDCs), turbine =ecers, drag disks, y-densitometers, spool pieces and video optical probes. The measurement items of the JAERI- and USNRC-i provided instruments-are listed in Tables A-2 and A-3, respectively. Location of each instrument _is shown in Figs. A-17 through A-34 l-i { i
JAER!-M 84 - 221 Table A-1 Principal Dimensions of Test Facility
- 1. Core Dimension (1) Quantity of Bundle 8 Bundles (2) Bundle Array 1x8 (3) Bundle Pitch 230 mm (4) Rod Array in a Bundle 16= 16 (5) Rod Pitch in a Bundle 14.3 mm (6) Quantity of Heater Rod in a Bundle 234 rods (7) Quantity of Non-Heated Rod in a Bundle 22 rods (8) Total Quantity of Heater Rods 234 = 8 = 1872 rods (9) Total Quantity of Non-Heated Rods 22 x 8 = 176 rods (10) Effective Heated Length of Heater Rod 3660 mm (11) Diameter of Heater Rod 10.7 mm (12) Diameter of Non-Heateed Rod 13.8 mm
- 2. Flow Area & Fluid Volume (1) Core Flow Area * (nominal) 0.227 m2
~
(2) Core Fluid Volume 0.92 m 3 (3) Baffle Region Flow Area 0.10 m 2 (4) Baffle Region Fluid Volume 0.36 m 3 2 (5) Downcomer Flow Area . 0.121 m 2 (6) Upper Annulus Flow Area 0.158 m (7) Upper Planum Hori:ontal Flow Area 0.525 m (8)' Upper Plenum Fluid Volume 1.16 m 3 (9) Upper Head Fluid Volume 0.86 3 (10) Lower Plenum Fluid Volume 1.38 m (11) Steam Generator Inlet Plenum Simulator Flow Area 0.626 m2 3 (12) Steam Generator Inlet Plenum Simulator Fluid Volume 0.931 m (13) Steam Water Separator Fluid Volume 5.3 m 3 (14) Flow Area at the Top Plate of Steam Generator 2 Inlet Plenum Simulator O.195 m (15) Hot Leg Flow Area 0.0826 m (16) Intact Cold Leg Flow Area (Diameter = 297.9 mm) 0.0697 m 2 (17) 3roken Cold Leg Flow Area (Diameter = 151.0 mm) 0.0179 m
- Flow area in the core is 0.35 m2 , including the excess flow area of gaps between the bundle and the surface of thermal insulator and between the core barrel and the pressure vessel vall. ,
JAER!-M 84 -221 , Table A-1 Principal Dimensions of Test Facility 3 (18) Containment Tank I Fluid Volume 30 m 3 (19) Containment Tank II Fluid Volume 50 m
- 3. Elevation & Height (1) Top Surface of Upper Core Support Plate (UCSP) 0m (2) Botton Surface of UCSP -76 mm (3) Top of the Effective Heated Length of Heater Rod -393 un (4) Bottom of the Skirt in the Lower lh enum -5270 mm (5) Bottos.of Intact Cold Leg +724 mm (6) Bottom of Hot Leg +1050 m (7) Top of Upper Plenum +2200 mm (8) Sottom of Steam Generator Inlet Plenum Simulator +1933 c:m (9) Centerline of Loop Seal Bottom -2281 =m (10) Bottom Surface of End' Box - 135.1 mm (11) Top of the Upper Annulus +2234 =m
~
(12) Height of Steam Generator Inlet Plenum Simulator - 15 9 5 = (13) Height of Loop Seal 3140 mm (14) Inner Height of Hot Leg Pipe' 737 mm (15) Bottom of Lower Plenum -5770 m (16) Top of Upper Head +2387 m
JAERI-M S4 - 221 Table A-2 Measurement Items of SCTF (JAERI-provided instruments) LOCATION ITEM PROBE fQUArJTITY
- 1. COPI center pressure DP cell i short range a: core I citi, press. OP cell J.
half length of Ocre diff. press. OP cell le full length of core diff. press. DP cell 8 across spacers diff. press. DP cell 7 across end box diff. press. DP cell 8 across 4 assemblies diff. press. DP cell 3 across 8 assemblies diff. press. DP cell 3 below and above end box steam velocity Pitot-tube 3 sub channel steam velocity Pitot-tube 13 below end box hole fluid temp. T/C 16 above end box hole fluid temp. T/C 16 core baffle fluid temp. T/C 6 - non-heating' rods fluid temp. T/C 96 steam temp. , SSP 16 clad temp. T/C 108 heater rods clad temp. T/C 640 side walls wall temp. T/C 36 core baffle wall tempf T/C 6-core baffle liquid level DP cell- 1 short range of core baffle liquid level DP cell 6 heated rod power , 8 sum (IO39)
- 2. UPPER PLENUM centre pressure DP cell 1 across end Dox tie plate diff. press. DP cell 8 cort autlet-hot Leo inlet diff. press. OP cell 4 periphery of -UCSP hole fluid temp. T/C A j l centre of UCSP nole fluid temp. T/C "
250mn & 1000mm acove UCSF fluid temp. T/C a surface'of UCSP fluid temp. T/C " above UCSP hole steam temp. SSP H
JAER!-M S4 -221 Table A-2 Measuremen t Items of SCTF (JAERI-provided instruments) (Continued) LCCATION ITEM PROBE QUANTITY f
! 15 surface of structure wall temp. fT/C 6 1
side walls wall temp. T/C 6 above end box tie plate liquid level DP cell a DP cell u above UCSP liquid level Pitot-tube 2 above UCSP (v.) steam velocity steam velocity Pitot-tube 2 inter-structures (h.)
- sum ( 97)
- 3. LCWER . PLENUM belew bottom spacer pressure DP cell 1 lower plenum diff. press. DP cell 1
- upper plenum core inlet fluid temp. T/C 8 inlet from downcomer fluid temp. T/C 2 side & bottom walls wall temp. T/C 4 -
below bottem spacer liquid level DP cell 1 sumf 171
- 4. DCWNCCME R upper po;sitien pressure DP cell, I horizontal direction diff. press. DP cell 1 fcur levels fluid temp. T/C 8 side wall wall temp. T/C 2 inner wall wall temp. T/C 2 below cold leg level liquid level DP cell 1 above cold leg level liquid level DP cell I below core inlet level liquid level DP cell I bottom momentum flux Drag disk 2 sum ( 19)
- 5. McT LEG !
full length l dif f. press . OP cell 1 ) multiple points fluid temp. T/C 3 steam temp. SSP 3 wall temp. T/C 1 I liquid level DP cell 2 l sum ( 10) ; l
JAERI-M 84 - 221 Table A-2 Measurement items of SCTF (JAERI-pr'ovided instruments) (Continued)
- LOCATION ITEM PROSE QUANTITY f
- 6. S/W SEPARATOR SIDE BROKEN COLD LEG across resistance diff. press. DP cell 1
. simulator.
S/W separator to contain- flow rate venturi 1 ment tank II multiple points fluid temp. T/C 1 steam temp. SSP 1 wall temp. T/C 1 sum ( 5) 7.. INTACT COLD LEG full length diff. press. DP cell 1 across resistance diff. press. DP cell 1 simulator . across pump simulator diff. press. DP cell 1 flow rate venturi 1 near resistance fluid temp. T/C 1 simulator pump simulator fluid temp. T/C 3 wall temp. T/C 1 sumt 9)
- 8. PV SIDE BRCKEN COLD-LEG pressure DP cell 1 full length diff. press. DP cell . 1 across resistance diff. press. DP cell 1 simulator multiple points fluid temp. T/C 4 f-i h- wall temp. T/C 2 r
liquid level DP cell 2 E sumt 11) l- 9. VENT LINE across the length diff. pres. DP cell 1-sumt 11
.f L3 -W _ ,
JAERI-M 84 -221 Table A-2 Measurement items of SCTF (JAERI-provided instruments) (Continued) LOCATION ITEM PROBE QUANTITY
- 10. S/W SEPARATOR pressure DP cell I between inlet and outlet diff. press. OP cell 1 SG plenum simulator diff. press. DP cell 1 2
SG plenum simulator fluid temp. T/C 2 top and bottom fluid temp. T/C T/C 2 wall wall temp. 1 full height liquid level DP cell 11guld extraction flow rate DP cell 1 sum ( 11)
- 11. CCNTAINMENT TANK-I 1
pressure DP cell downcemer-CT-I diff. press. OP cell 1 , diff. press. DP cell I CT-I - CT-II DP cell 1 flow rate DP cell 1 full height liquid level 1 float 3 top, middle & bottom fluid temp. T/C sail- wall temp. T/C 1 sum ( 10)
&2. ' CCNTAINMEN"' TANK-II pressure . DP cell 1 1
upper plenum - CT-II - diff. press. OP cell diff. press. OP cell I separator - CT-II DP cell 1 r steam blow line flow rate DP cell 1 full height liquid level . top, middle & - tottom flutd temp. T/C / sum ( 3 al I 1 8
- 13. ECC. INJECTION SYST!M DP cell 1 ACC tank pressure E-M flow meter 2 total and LPCI flow rate 1
ACC tarx fluid temp. T/C 1 3 JAERI-M 84 - 221 Table A-2 Measurement items of SCTF (JAERl-provided ' instruments) (Continued) I ITEM PROBE j LOCATION QUANTITY l
- 13. ECC INJECTION SYSTEM header fluid temp. T/C 2 ACC cank 11guld level DP cell 1 samt 8) 14 UCSP WATER EXTRACTION SYSTEM extraction line flow rate E-M flow meter 4 I steam line flow rate DP cell 4 extraction line fluid temp. T/C 5 steam line fluid temp. T/C 1 extraction line liquid level DP cell 4 sum ( 19)
- 15. SATURATED WATER TANK
~
fluid temp T/C 1 liquid level DP cell 1 sum ( 2)
- 16. NITROGEN GAS SYSTEM flow rate DP cell 1
-> injection port fluid temp. T/C 1 I sumt 2)
I Total 1267 t t
. - =
JAERI-M 84 - 221 Table A-3 Measurement Items of SCTF (USNRC-provided instruments) LOCATION' ITEM PRCBE QUANTITY l 1. CORE !, l non-heated rods lliquidlevel LLD 20=4 = 80 non-heated rods film thicknes s film probe 6 and velocity non-heated rods void fraction and flag probe 8 droplet velocity 8 side' walls film thickness film probe and velocity sub-channel fluid density Y-densitometer 10 end box fluid density Y-densitometer 5 flow pattern video optical 1 and box probe
- 2. UPPER PLENUM full height liquid level roc 8x8 = 64 .
structure surface film thickness film prebe 6 and velocity side walls film thickness film probe 6 and velocity
', inter s tr*:cture void fraction prong pecbe 8 turbine 8 above UCSP hole velocity 'veloc2ty turbine 4 Inter structure r
inter structure fluid density Y-densitemeter 4 l hot' leg inlet flow pattern video optical 1 probe l
- 3. LOWER PLENUM velocity turbine 4 core inlet bottom reference reference probe .1 conductivity i
- 4. DOWNCCMER i full' height liquid level. TDC 2x 3x7 = 42 I
'two levels ; velocity drag disk 3 string probe 3 two levels { void fraction l-g - so -
JAERI-M 84 -221 ( Table A-3 Measurement Items of SCTF (USNRC-provided instruments) (Continued)
' LOCATION ITEM PRCBE QUANTITY
- 5. HOT LEO mass flow ra'te spool piece '
fluid density void fraction
- 6. PV SIDE BRCKIN COLD-LEG mass flow rate spool piece I fluid density void fraction 7 VENT LIbT mass flow rate spool piece 1 void fraction 9
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~1 Elevolion No ' Horizontal location tievcIlon in bundle (mm) l Region No ; 3660 6 Sundle No.
Elevation No. Fluid tempera tu re Horizontal location in bundle Type 2 ; 2760+ 5 . ( TW --- 11 ) s , .,
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9 a F ig. A-24 Thermocouple Loe sti ons o f Tempe ra tu re Mes su remen t s in Pressure Vessel e x cep t Core Re gion (Ve r tic al Vi ew)
- 103 -
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(the bottom of downcomer is blocked) (2) used for the other tests Fig. A-25 1.ocation of Pressure Measurements in Pressure Vessel. Dif f erential . Pressure Measurements between Upper and lower Plenues and Liquid Level Measurements in Downcomer and 1.ouer Planum
- 104 -
JAERI .\f 84 - 2 i 7847 (20771 i SM
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5778(8) Licuid level above UCSP 5770 (0)
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- 105 -
JAERI .\f 84 -221 End bax tie plate i Grid spaccr 5538f382tl n llh I
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5377(3660! am 5077(33601 ssi 5052(3335) jr4 , l Spacer 6 2G235) MS DTO OTO,S
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Acmss Core Core Between core spacer half full' spacer g height Bundle o Fi9. A-27 Locacion, of y*' 1c81 Dif ferencial Pressure Hessurements in Core
- 106 -
JAERI-M 84 -221
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Core I I i HWL- i i l Bundle t 2 I 13i4'51 i .. I 68I 7I8 I baffle Fig. A-28 Locations of Horizontal Differential Pressure Haasurements in Core. and Dif f erential Pressure Measurements between End Box and Inlet of Hot Leg
- 107 -
L
JAERI-M 84 -221 ll TF03-HWS PS I 80011 l TE03- HWS V.W LT02 - HS oO I TF02-HWS h/ , 2074.5 \ /' 762 4'* . _r h . E r1 / .^ ok '
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TE02 - HW S Location lToo no. I l DTot HS l P5'- Intet of hot leg"' I DT01 G S l P5'- Ercken cold leg (S-w seccreter side)* OT02G S l P5"- S-w seccrutor tank' t Fig. A-29 Locacions of woe Leg In:.crimentation
- 108 -
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JAERI .\l 84 - 221 Appendix C Selected Data of Test Sl-SH4 (Run 529) Fig. No. Measurement item C- 1 % C-16 Heater rod temperature C-17 % C-20 Fluid temperature in core C-21 % C-22 Steam temperature in core C-23 % C-24 Fluid temperature just above end box tie place C-25 % C-2S Fluid temperature in UCSP holes C-29 % C-30 Fluid temperature on UCSP surface C-31 % C-32 Fluid temperature above UCSP C-33 % C-34 Fluid temperature at core inlet C-35 Fluid temperature in downcomer C-36 Fluid temperature in hot leg C-37 Fluid temperature in intact cold leg C-38 Fluid temperature in broken cold leg (steam / water separator side) C-39 Fluid te=perature in broken cold leg'(PV side) C-40 Liquid level in downcomer
~
C-41 % C-42 Liquid level above end box tie plate . C-43 % C-44 Liquid level above UCS? C-45 Liquid level in hot leg C-46 Liquid level in broken cold leg (PV side) C-47 % C-48 Differential pressure of core full height-C-49 % C-30 Differential pressure across end box the plate C-51 % C-52 Horizontal differential pressure in core C-53 Differential pressure of hot leg C-54 Differential pressure across steam / water separator C-55 Differencial pressure of intact cold leg C-56 Differential pressure between steam / water separator and containment tank-II C-57 Differential pressure between top of upper plenum and containment tank-II C-58 Differential pressure between containment tanks I and II C-59 Differential pressure of broken cold leg (?V side) C-60 Pressures in pressure vessel C-61, C-62 Sundle powers C-63 ECC injection rate into intact cold leg C-64 ECC injection race into upper plenum C-65 % C-70 Void fractions in core
-133-
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