NUREG/IA-0027

AEEW-M2464

International

Agreement Report

TRAC-PFl/MODi Calculations of

LOFT Experiment LP-02-6

Prepared by

P. Coddington, C. Gill

Winfrith Technology Centre

United Kingdom Atomic Energy Authority

Winfrith, Dorchester

Dorset, England DT 28 DH

Office of Nuclear Regulatory Research

U.S. Nuclear Regulatory Commission

Washington, DC 20555

April 1992

Prepared as part of

The Agreement on Research Participation and Technical Exchange

under the International Thermal-Hydraulic Code Assessment

and Application Program (ICAP)

Published by

U.S. Nuclear Regulatory Commission
NOTICE

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their employees, makes any warranty, expressed or implied, or

assumes any legal liability or responsibility for any third party's

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Available from

Superintendent of Documents

U.S. Government Printing Office

P.O. Box 37082

Washington, D.C. 20013-7082

and

National Technical Information Service

Springfield, VA 22161
NUREG/IA-0027 AEEW-M2464

International ~WM4

Agreement Report

TRAC-PF1/MODi Calculations of

LOFT Experiment LP-02-6

Prepared by

P. Coddington, C. Gill

Winfrith Technology Centre

United Kingdom Atomic Energy Authority

Winfrith, Dorchester

Dorset, England DT 28 DH

Office of Nuclear Regulatory Research

U.S. Nuclear Regulatory Commission

Washington, DC 20555

April 1992

Prepared as part of

The Agreement on Research Participation and Technical Exchange under the International Thermal-Hydraulic Code Assessment

and Application Program (ICAP)

Published by

U.S. Nuclear Regulatory Commission
NOTICE

This report is based on work performed under the sponsorship of the

United Kingdom Atomic Energy Authority. The information in this

report has been provided to the USNRC under the terms of the

International Code Assessment and Application Program (ICAP)

between the United States and the United Kingdom (Administrative

Agreement - WH 36047 between the United States Nuclear Regulatory

Commission and the United Kingdom Atomic Energy Authority Relating

to Collaboration in the Field of Modelling of Loss of Coolant

Accidents, February 1985). The United Kingdom has consented to the

publication of this report as a USNRC document in order to allow

the widest possible circulation among the reactor safety community.

Neither the United States Government nor the United Kingdom or any

agency thereof, or any of their employees, makes any warranty,

expressed or implied, or assumes* any legal liability of

responsibility for any third party's use, or the results of such

use, or any information, apparatus, product or process disclosed

in this report, or represents that its use by such third party

would not infringe privately owned rights.
AEEW - M 2464

TRAC-PF1/MOD1 CALCULATIONS OF LOFT EXPERIMENT LP-02-6

P CODDINGTON

C GILL

SUMMARY

The report describes four TRAC-PF1/MOD1 calculations modelling

the OECD-LOFT experiment LP-02-6. This was a 200% double-ended

cold leg break experiment performed at nearly full power (47 MW)

and with a loop mass flow of 248 kg/s. In the experiment the

pumps were tripped and then allowed to coast down naturally after

the start of the transient. Two of the calculations compared the

results of two versions of the code (12.2 and 13.0), one

incorporated a reduced gap between the fuel and the cladding to

reduce the initial fuel stored energy, and the other had the TRAC

interface sharpener model switched off.

Following the opening of the quick acting blowdown relief valves

to initiate the transient there is a net flow out of the vessel

until about 4 seconds, at which time the broken loop cold leg

flow out-of the vessel drops below the flow into the vessel from

the intact loop cold leg, being driven by the pumps' inertia.

This net flow into the vessel, enhanced by flashing of subcooled

liquid in the downcomer and lower plenum, causes a bottom-up flow

of liquid and quenches about 2/3 of the core. Additionally a

top-down partial quench, extending to about the 30 inch

elevation, is observed at about 15 seconds. This corresponds to

fluid running back into the upper plenum and down into the core

as the fluid in the pressurizer and steam generator begins to

flow back along the intact loop hot leg.

The nature of the observed quenching is not entirely clear: it

may be genuine fuel pin quenching or simply localised quenching

of the thermocouples.

At 17.5 seconds, the primary system pressure reaches 42 bars, at

which point the Emergency Core Cooling System trips.

Measurements suggest oscillatory flow immediately upstream of the

accumulator injection point in the intact loop cold leg. Except

for two slugs of liquid, totalling about 200-250 kg, compared to

a total accumulator flow of about 1,690 kg, no continuous

bypassing of the downcomer by the accumulator fluid occurs.

Most of it finds its way to the lower plenum. As the water level

here rises, it begins to quench the bottom of the core at about

37 seconds and the quench moves progressively upwards. The final

quench of the uppermost elevations is coincident with the entry

of accumulator nitrogen into the intact loop cold leg and the

consequent rise in the primary system pressure.

AEEW - M 2464 iii
-'-SUMMARY (Continued)

All four TRAC calculations predict similar hydraulic behaviour to

each other. The bottom-up liquid flow at 4 seconds extends to

the top of the core, as opposed to just 2/3'of the way up as in

the experiment. The TRAC modelling does not predict either the

bottom-up or the top-down quench at 15 seconds and following the

subsequent fuel rod dryout the calculated temperatures are too

high, particularly at the top and bottom of the fuel rods. The

reduced fuel-gap calculations (ZEROGAP and ISHARP) are

considerably better in this respect due to their lower stored

energy. The calculations predict no bypass of ECCS fluid in line

with the experiment and all predict oscillatory core inlet flow.

There were differences, however, in the behaviour of fluid in the

intact loop cold leg, for in some of the calculations the

production of liquid slugs was predicted, in others it was not.

These differences are believed to be due to the sensitivity of

the TRAC condensation model rather than any specific changes to

the models.

All the calculations predict a surge of fluid into the core on

the entry of nitrogen into the intact loop cold leg. However,

the higher rod temperatures in the calculations mean that the

final quench is delayed longer than in the experiment.

The main differences between the calculations are therefore

restricted to the thermal behaviour of the fuel rods due for

example to the different dispersed flow heat transfer used in

versions 12.2 and 13.0 and the reduced fuel stored energy in the

ZEROGAP and ISHARP calculations.

Reactor Systems Analysis Division

AEE Winfrith

August 1987

AEEW - M 2464 i V
CONTENTS

PAGE

1 INTRODUCTION 1

2 TRAC INPUT MODEL AND CALCULATIONS 1

3 TRAC CALCULATIONS 2

4 INITIAL CONDITIONS 3

5 ANALYSIS OF LP-02-6 TRANSIENT 4

(i) SEQUENCE OF EVENTS 4

(ii) TRAC CALCULATIONS 6

(iii) "JONS" AND "ORIGINAL" CALCULATIONS 6

LOOP BEHAVIOUR 6

VESSEL HYDRAULIC AND THERMAL 10

BEHAVIOUR

CORE THERMAL RESPONSE - CENTRAL BUNDLE 12

- PERIPHERAL BUNDLES 15

(iv) "ORIGINAL" AND "ZEROGAP" CALCULATIONS 17

(v) "ZEROGAP" AND "ISHARP" CALCULATIONS 20

6 SUMMARY AND CONCLUSIONS 22

7 ACKNOWLEDGEMENTS 25

8 REFERENCES 26

AEEW- M 2464 V
FIGURES1 Major Components of Loft System

2 Loft Piping Schematic with Instrumentation

3 Intact Loop Nodalisation

4 Broken Loop Nodalisation

5 Steam Generator Secondary Nodalisation

6 Reactor Vessel Nodalisation

NB Figures 7-77 refer to "JONS", "ORIGINAL" and

Experimental Data

7 Broken Loop Cold Lea (BL-1) - Pressure

8 Broken- Loop

9

10

11

12

13

14

15

16

17

18

19.

20

21

22

23

Broken Loop

Broken Loop

Broken Loop

Broken Loop

Broken Loop

Broken Loop

Broken Loop

Broken Loop

Broken Loop

Broken Loop

Broken. Loop

Intact Loop

Intact Loop

Intact Loop

Intact Loop

Cold

Cold

Cold

Cold

Cold

Cold

Hot

Hot

Hot

Hot

Hot

Hot

Cold

Cold

Cold

Cold

Cold

Leg (BL-1)

Leg (BL-l)

Leg (BL-1)

I Leg-(BL-I)

Leg (BL-4)

Leg (BL-8)

Leg (BL-2)

Leg (BL-2)

Leg (BL-2)

Leg (BL-2)

Leg (BL-2)

Leg (BL-3)

Leg (PC-i)

Leg (PC-i)

Leg (PC-i)

Leg (PC-i)

Leg (PC-l)

- Mixture Density

- Mass Flow Rate

- Liquid Temperature

- Vapour Temperature

- Pressure

- Pressure

- Pressure

- Mixture Density

-. Mass Flow Pate

- Liquid Temperature

- Vapour Temperature

- Pressure

- Mixture Density

- Mass Flow Rate

- Liquid Velocity

- Liquid Temperature

24 Intact Loop - Vapour Temperature

25 Pump Speed

AEEW - M 2464 vi
FIGURES (Continued)

26 Intact Loop Hot Leg (PC-2) - Mixture Density

27 Intact Loop Pot Leg (PC-2) - Mass Flow Rate

28 Intact Loop Hot Leg (PC-2) - Liquid Temperature

29 Intact Loop Hot Leg (PC-2) - Vapour Temperature

30 Intact Loop Pot Leg (PC-2) - Pressure

31 Intact Loop Hot Leg - Pressurizer Pressure

32 Intact Loop Hot Leg - Pressurizer Water Level

33 Emergency Core Cooling System - Accumulator Water Level

34 Emergency Core Cooling System - Accumulator Pressure

35 Upper Plenum Pressure

36 Lower Plenum Liquid Axial Velocity

37 Upper Plenum Liquid Axial Velocity

38 Downcomer Liquid Temperature at 5.0 m

39 Downcomer Liquid Temperature at 4.2 m

40 Downcomer Liquid Temperature at 2.4 m

41 Downcomer Liquid Temperature at 0.3 m

42 Lower Plenum Momentum Flux

43 Core Inlet Mass Flow

44 Core Outlet Mass Flow

45 Core Liquid Volume Fraction

.46 Lower Plenum Liquid Volume Fraction

47 Downcomer Liquid Volume Fraction

48 Core Liquid Mass

49. Vessel Liquid Mass

50 Total Rod Heat Flux

51 Total Slab Heat Flux

AEEW - M 2464 vii
FIGURES (Continued)

52

53

54

55

56

57

58

59

60

61

62

63

64

65

66

67

68

69

70

71

72

73

74

75

76

Lower Plenum Average Liquid Temperature

Cladding Temperature at 2 Inch Elevation (Central Bundle)

Cladding Temperature at 11 Inch Elevation (Central Bundle)

Cladding Temperature at 21 Inch Elevation (Central Bundle)

Cladding Temperature at 24 Inch Elevation (Central Bundle)

Cladding Temperature at 27 Inch Elevation (Central Bundle)

Cladding Temperature at 31 Inch Elevation (Central Bundle)

Cladding Temperature at 39 Inch Elevation (Central Bundle)

Cladding Temperature at 43.8 Inch Elevation (Central

Bundle)

Cladding Temperature at 49 Inch Elevation (Central Bundle)

Cladding Temperature at 62 Inch Elevation (Central Bundle)

Centreline Temperature at 27 Inch Elevation (Central

Bundle)

Cladding Temperature at

Cladding Temperature at

Cladding Temperature at

Cladding Temperature at

Cladding Temperature at

Cladding Temperature at

Cladding Temperature at

Cladding Temperature at

Cladding Temperature at

Cladding Temperature at

Cladding Temperature at

Cladding Temperature at

Cladding Temperature at

11

21

30

39

49

11

21

28

39

11

30

26

39

Inch Elevation

Inch Elevation

Inch Elevation

Inch Elevation

Inch Elevation

Inch Elevation

Inch Elevation

Inch Elevation

Inch Elevation

Inch Elevation

Inch Elevation

Inch Elevation

Inch Elevation

(Bundle 2)

(Bundle 2)

(Bundle 2)

(Bundle 2)

(Bundle 2)

(Bundle 4)

(Bundle 4)

(Bundle 4)

(Bundle 4)

(Bundle 6)

(Bundle 6)

(Bundle 6)

(Bundle 6)

AEEW - M 2464 Viii
FIGURES (Continued)

77 Cladding Temperature at 45 Inch Elevation (Bundle 6)

NB Figures 78-148 refer to "ORIGINAL", "ZEROGAP" and

Experimental Data

78 Broken Loop Cold Leg (BL-I) - Pressure

79

80

81

82

83

84

85

86

87

88

89

90

91

92

93

94

Broken Loop

Broken' Loop

Broken

Broken

Broken

Broken

Broken

Broken

Broken

Broken

Broken

Broken

Intact

Intact

Intact

Intact

Loop

Loop

Loop

Loop

Loop

Loop

Loop

Loop

Loop

Loop

Cold Leg

Cold Leg

Cold Leg

Cold Leg

Cold Leg

Cold Leg

Hot Leg

Hot Leg

Hot Leg

Hot Leg

Hot Leg

Hot Leg

(BL-1)

(BL-1)

(BL-i)

(BL-I)

(BL-4)

(BL-8)

(BL-2)

(BL-2)

(BL-2)

(BL-2)

(BL-2)

(BL-3)

(PC-l)

(PC-l)

(PC-i)

(PC-i)

(PC-l)

) - Mixture Density

- Mass.Flow Rate

- Liquid Temperature

- Vapour Temperature

- Pressure

- Pressure

- Pressure

- Mixture Density

- Mass Flow Rate

- Liquid Temperature

- Vapour Temperature

- Pressure

- Mixture-Density

- Mass Flow Rate

- Liquid Velocity

- Liquid Temperature

- Vapour Temperature

Loop Cold Leg

Loop Cold

Loop Cold

Loop Cold

Leg

Leg

Leg

95 Intact Loop Cold Leg

96

97

98

99

100

101

Pump Speed

Intact Loop Hot Leg

Intact Loop Hot Leg

Intact Loop Hot Leg

Intact Loop Hot Leg

Intact Loop Hot Leg

(PC-2)

(PC-2)

(PC-2)

(PC-2)

(PC-2)

- Mixture Density

- Mass Flow Rate

- Liquid Temperature

- Vapour Temperature

- Pressure

AEEW - M 2464 ix
FIGURES (Continued)

102 Intact Loop Hot Leg - Pressurizer Pressure

103 Intact Loop Hot Leg - Pressurizer Water Level.

104 Emergency Core Cooling System - Accumulator Water Level

105 Emergency Core Cooling System - Accumulator Pressure

106 Upper Plenum Pressure

107 Lower Plenum Liquid Axial Velocity

108 Upper Plenum Liquid Axial Velocity

109 Downcomer Liquid Temperature at 5.0 m

110 Downcomer Liquid Temperature at 4.2 m

111 Downcomer Liquid Temperature at 2.4 m

112 Downcomer Liquid Temperature at 0.3 m

113 Lower Plenum Momentum Flux

114 Core Inlet.Mass Flow

115 Core Outlet Mass Flow

116 Core Liquid Mass

117 Lower Plenum Liquid Volume Fraction

118 Downcomer Liquid Volume Fraction

119 Core Liquid Volume Fraction

120 Vessel Liquid Mass

121 Total Rod Heat Flux

122 Total Slab Heat Flux

123 Lower Plenum.Average Liquid Temperature

124 Cladding Temperature at 2 Inch Elevation (Central Bundle)

125 Cladding Temperature at 11 Inch Elevation (Central Bunlde)

126 Cladding Temperature at 21 Inch Elevation (Central Bundle)

127 Cladding Temperature at.24 Inch Elevation (Central Bundle)

AEEW - M 2464 X
FIGURES (Continued)

128

129

130

131

132

133

134

135

136

137

138

139

140

1.41

142

143

144

145

146

147

148

Cladding Temperature at 27 Inch Elevation (Central Bundle)

Cladding Temperature at 31 Inch Elevation (Central Bundle)

Cladding Temperature at 39 Inch Elevation (Central Bundle)

Cladding Temperature at 43.8 Inch Elevation (Central

Bundle)

Cladding Temperature at 49 Inch Elevation (Central Bundle)

Cladding Temperature at 62 Inch Elevation (Central Bundle)

Centreline Temperature at 27 Inch Elevation (Central

Bundle)

Cladding Temperature at

Cladding Temperature at

Cladding Temperature at

Cladding Temperature at

Cladding Temperature at

Cladding Temperature at

Cladding Temperature at

Cladding Temperature at

Cladding Temperature at

Cladding Temperature at

Cladding Temperature at

.Cladding Temperature at

Cladding-Temperature at

Cladding Temperature at

11

21

30

39

49

11

21

28

39

11

30

26

39

45

Inch Elevation

Inch Elevation

Inch Elevation

Inch Elevation

Inch Elevation

Inch Elevation

Inch Elevation

Inch Elevation

Inch Elevation

Inch Elevation

Inch Elevation

Inch Elevation

Inch Elevation

Inch Elevation

(Bundle 2)

(Bundle 2)

(Bundle 2)

(Bundle 2)

(Bundle 2)

(Bundle 4)

(Bundle 4)

(Bundle 4)

(Bundle 4)

(Bundle 6)

(Bundle 6)

(Bundle 6)

(Bundle 6)

(Bundle 6)

149

150

151

NB Figures 149-219 refer to "ISHARP", "ZEROGAP" and

Experimental Data

Broken Loop Cold Leg (BL-l) - Pressure

Broken Loop Cold Leg (BL-1) - Mixture Density

Broken Loop Cold Leg (BL-1) - Mass Flow Rate

AEEW - M 2464 Xi
FIGURES (Continued)

152

153

154

155

156

157

158

159

160

161

162

163

-164

165

166

167

168

169

170

171

172

173

Broken Loop

Broken Loop

Broken Loop

Broken Loop

Broken Loop

Broken Loop

Broken Loop

Broken Loop

Broken Loop

Broken Loop

Intact Loop

Intact Loop

-- Intact Loop

Intact Loop

Intact Loop

Pump Speed

Intact Loop

Intact Loop

Intact Loop

Intact Loop

Intact Loop

Intact Loop

Cold Lee

Cold Lec

Cold Lec

Cold Les

Hot Leg

Hot Leg

Hot Leg

Hot Leg

Hot Leg

Hot Leg

Cold Leg

Cold Leg

Cold Leg

Cold Leg

Cold Leg

(BL-1) - Liquid Temperature

(BL-1) - Vapour Temperature

(BL-4) - Pressure

(BL-8) - Pressure

(BL-2) - Pressure

(BL-2) - Mixture Density

(BL-2) - Mass Flow PRte

(BL-2) - Liquid Temperature

(BL-2) - Vapour Temperature

(BL-3) - Pressure

(PC-i) - Mixture Density

(PC-i) - Mass Flow Rate

(PC-!) - Liquid Velocity

(PC-i) - Liquid Temperature

(PC-I) - Vapour Temperature

(PC-2) - Mixture Density

(PC-2) - Mass Flow Rate

(PC-2) - Liquid Temperature

(PC-2) - Vapour Temperature

(PC-2) - Pressure

Hot

Hot

Hot

Hot

Hot

Leg

Leg

Leg

Leg

Leg

Hot Leg - Pressurizer Pressure

174 Intact Loop Hot Leg - Pressurizer Water Level

175 Emergency Core Cooling System - Accumulator Water Level

176 Emergency Core Cooling System - Accumulator Pressure

177 Upper Plenum Pressure

AEEW - M 2464 xii
FIGURES (Continued)

178 Lower Plenum Liquid Axial Velocity

179 Upper Plenum Liquid Axial Velocity

180 Downcomer Liquid Temperature at 5.0 m

181 Downcomer Liquid Temperature at 4.2 m

182 Downcomer Liquid Temperature at 2.4 m

183 Downcomer Liquid Temperatue at 0.3 m

184 Lower Plenum Momentum Flux

185 Core Inlet Mass Flow

186 Core Outlet Mass Flow

187 Core Liquid Mass

188 Lower Plenum Liquid Volume Fraction

189 Downcomer.Liquid Volume Fraction

190 Core Liquid Volume Fraction

191 Vessel Liquid Mass

192 Total Rod Heat Flux

193 Total Slab Heat Flux

194 Lower Plenum Average Liquid Temperature

195 Cladding Temperature at 2 Inch Elevation (Central Bundle)

196 Cladding Temperature at 11 Inch Elevation (Central Bundle)

197 Cladding Temperature at 21 Inch Elevation (Central Bundle)

198 Cladding Temperature at 24 Inch Elevation (Central Bundle)

199 Cladding Temperature at 27 Inch Elevation (Central Bundle)

200 Cladding Temperature at 31 Inch Elevation (Cent ral Bundle)

201 Cladding Temperature at 39 Inch Elevation (Central Bundle)

.202 Cladding Temperature at 43.8 Inch Elevation (Central Bundle)

203 Cladding Temperature at 49 Inch Elevation (Central Bundle)

AEEW - M 2464 xiii
FIGURES (Continued)

204 Cladding Temperature at 62 Inch Elevation (Central Bundle)

205 Centreline Temperature at 27 Inch Elevation (Central

Bundle)

206

207

208

209

210

211

212

213

214

215

216

217

218

Cladding

Cladding

Cladding

Cladding

Cladding

Cladding

Cladding

Cladding

Cladding

Cladding

Cladding

Cladding

Cladding

Temperature at

Temperature at

Temperature at

Temperature at

Temperature at

Temperature at

Temperature at

Temperature at

Temperature at

Temperature at

Temperature at

Temperature at

Temperature at

11

21

30

39

49

11

21

28

39

11

30-

26

39

Inch

Inch

Inch

Inch

Inch

Inch

Inch

Inch

Inch

Inch

Inch

Inch

Inch

Elevation

Elevation

Elevation

Elevation

Elevation

Elevation

Elevation

Elevation

Elevation

Elevation

Elevation

Elevation

Elevation

(Bundle

(Bundle

(Bundle

(Bundle

(Bundle

(Pundle

(Bundle

(Bundle

(Bundle

(Bundle

(Bundle

(Bundle

(Bundle

2)

2)

2)

2)

2)

4)

4)

4.)

4)

6)

6)

6)

6)

219 Cladding Temperature at 45 Inch Elevation (Bundle 6).

AEEW - M 2464 xiv
TABLES

1 Matrix of Input Data

2 Initial Conditions for Experiment LP-02-6

3 Chronology of Events for Experiment LP-02-6

4 Core Axial Fine Mesh Elevations and Relative Power Density

AEEW - M 2464 

xv

COMMERCIAL INT CONFIDENCE

1 INTRODUCTION

This report provides a description of the results of four

TRAC-PF1/MODl calculations of the OECD-LOFT experiment LP-02-6.

This experiment was the third of the high power LOFT large break

experiments (L2-3 and L2-5 being .the previous two experiments)

and although it was performed at the beginning of the OECD-LOFT

project, the boundary conditions for the experiment were

specified by the USNRC. The primary boundary conditions that

distinguish this experiment from the previous experiments L2-3

and L2-5 were the increased power, ie 47 MW and the fact that the

primary coolant pumps were tripped but not decoupled from their

flywheel systems at the start of the transient. This resulted in

a positive (bottom-up) core flow during the blowdown period, ie

at about 5 secs, but the magnitude of this flow was less than

that observed in the earlier experiment L2-3 where the pumps

where kept running, such that the fuel rod external thermocouples

quenched immediately only in the bottom 2/3 rds of the central

fuel assembly. The remainder of the core (ie the top 1/3 rd)

quenched subsequently during the top-down flow period after about

12 secs.

A description of the LP-02-6 experiment can be found in the Quick

Look Report, Ref 1.

2 TRAC INPUT MODEL AND NODALISATION

Diagrams showing the LOFT facility and instrument locations are

given in'Figs 1 and 2 while noding diagrams of the TRAC

representation of the LOFT facility are shown in Figs 3, 4, 5 and

6 for all the calculations presented in this report, all of which

used the same nodal representation. The noding scheme and input

model is based upon the original TRAC-PD2 model which was

modified for TRAC-PFI/MOD1 at LANL for the analysis of L2-3 and

at AEEW for the analysis of LP-LB-l (Ref 2). However subsequent

to the analysis of LP-LB-1 the input deck was modified (Ref 3) to

improve the modelling in the areas of:-

(i) Primary coolant loop and vessel flow resistance.

(ii) Renodalisation of the ECCS injection line (Ref 4).

(iii) Revision of the fluid volumes and flow areas within the

reactor vessel.

(iv) Inclusion of core bypass paths in the reactor vessel (lower

plenum and core to upper plenum and downcomer to upper

plenum).

(v) Revision of the vessel metal-work heat structures (Ref 5).

(vi) A revision and inclusion of ambient heat losses.

All of the above are likely to have an influence on the

calculated results when compared to those calculated for

experiment LP-LB-1 and in fact some of the revisions, eg (i),

AEEW - M 2464 1
(ii) and (v) were a result of recognised inadequacies of that

analysis (see Pefs 2 and 3).

The results of the renodalisation of the ECCS line can be seen in

Fig 3, and the inclusion of the lower plenum and core to upper

plenum bypass in Fig 6i. Also shown in Figs 3 and 4 is the

,.location of the experimental measurement rakes in the intact and

broken loop hot and cold legs.

3 TRAC CALCULATIONS

As stated above, this report contains the results of four

TRAC-PFl/MODl calculations, these were performed sequentially and

the results of the calculations are presented in three groups

each containing a pair of calculations together with the

experimental data where appropriate. This report therefore

provides both the results of a limited sensitivity study together

with a comparison of the TRAC calculations with the experimental

data.

The four TPAC calculations, identified by their differences, are

as follows:-

(1) A calculation using the 'Standard' Winfrith version of

TRAC-PFl/MODl, Version 12.2 (ie code version UK reference

X26). This calculation used the "as manufactured" fuelclad gap of 100 von, on the figures this calculation is

labelled "JON'S" and is the subject of a separate report

(Ref 6).

(2) The above calculation was repeated using the Winfrith

version of TRAC-PFl/MODl Version 13.0 (ie code version UK

Reference B03). This calculation is labelled "ORIGINAL" on

the figures.

(3) Calculation (2) was repeated but with the "fuel-clad" gap

reduced to zero to reduce the steady state fuel stored

energy and hence the peak cladding temperatures during

blowdown. This calculation is labelled "ZERO-GAP" on the

figures.

(4) Finally calculation (3) was repeated but with the

TRAC-PF1/MOD1 core interface sharpener logic removed. The

core interface sharpener logic is a facility for

overwriting the axial mass flux in the core calculated from

the constitutive relations with an externally imposed model

to produce a,"sharp" core liquid level. The interface

sharpener restricts the axial flow of liquid in the core by..

limiting the core-cell exit void fraction to be greater

than 90% irrespective of that calculated by the

constitutive relations. The operation of the interface

sharpener has been seen to produce unphysical behaviour

during blowdown when applied to reactor calculations and to

produce too sharp a liquid vapour interface during reflood

(Ref 7). Its use is therefore not currently recommended.

This calculation is labelled "ITH--RP" in the figures.

AEEW - M 2464 2
A review of the four calculations is given in Table 1.

4 INITIAL CONDITIONS

- The initial conditions for experiment LP-02-6 and the calculated

transients are given in Table 2. The data for the experiment was

taken from the Experiment Quick LooK Report (Ref 1) and the

Experiment Specification Document (Ref 8). The data for the TRAC

calculations was taken from the "ZERO-GAP" calculation which was

the calculation used as the submission to the OECD-LOFT LP-02-6

experiment comparison exercise (Ref 9). There are no significant

differences between the initial conditions of the four

calculations and in fact transient calculations 3 and 4 used the

same steady-state calculation.

One major difference between this series of calculations and all

previous TRAC calculations, ie PD2 L2-3 and L2-5 (Ref 10) and

PFl/MODl LP-LB-1 (Ref 2) and LP-02-6 (Ref 11) calculations is the

improvement in the bypass modelling. As we see from Table 2, for

example, the total calculated bypass of - 10% is divided into a

lower plenum to upper plen.um bypass .of 2.6%, a downcomer to upper

plenum bypass of 2.26% with the remainder, 5.25%, flowing through

the Reflood Assist Bypass Valves (RABV). Previously only the

flow through the RABVs was represented.

The power was increased in experiment LP-02-6 from the 36 MW used

in L2-3 and L2-5, to 47 MW, an increase of - 1.3. However the

flow rate was only increased by - 25% from 200 kg/sec to 250

kg/sec, producing therefore a slightly increased temperature rise

across the core. The contrasts with experiment LP-LB-l where the

loop flow rate was increased to 300 kg/sec for a small (49

compared to 47 MW) increase in core power, producing a

significantly smaller core,AT.

The relative magnitude of loop flow and core power is likely to

influence the vessel hydraulic behaviour during blowdown, as is

the bypass representation for the calculated transients.

The total accumulator liquid available in experiment LP-02-6 wal

1.69 m4 which il lower than that for experiments L2-5 (1.96 m )

and L2-3 (2.166 m ), but higher than that of experiment LP-LB-l

(1.18 m4) (Ref 12). Thele numbers should be compared with the

* vessel volumes of 0.68 m for the lower plenum, 1.017 m4 for the

* : downcom~r (this number was significantly increased from that.of

0.672 m used in previous TRAC analyses of LOFT) and 0.272 m4 for

the core.

As will be seen from Table 2 the accumulator gas volume used in

the calculatio9 is significantly sTaller than the experimental

value (0.642 m compared to 0.95 m.-). This difference was

introduced into the input deck to compensate for the fact that

the TRAC code places a lower limit on the Nitrogen gas

temperature of 273 k (O0C) ie the freezing point of water, and.

that the gas temperature will .fall well below this value during

the emptying of the accumulators.

AEEW - M 2464 3
Apart from the above accumulator gas volume difference, Table 2

shows that the TRAC calculated initial conditions for the primary

circuit are within the uncertainty levels of the corresponding

measured quantities. There is however a small difference in the

pressuriser volumes used in the calculations (liquid 0.555, steam

0.376 m3 ) compareed to those for the experiment (liquid 0.607,

steam 0.39-m").

5 ANALYSIS OF LP-02-6 TRANSIENT

5(i) Secuence of Events

••he sequence of the significant events for LOFT experiment

LP-02-6 are listed in Table 3, where the times of occurrence are

compared with the times predicted by the "ZERO-GAP" TRAC

calculation. This is the same calculation as that for which the

initial conditions were presented in Table 2.

Experiment LP-02-6 was initiated (0.0 secs) by the opening of the

quick-opening blowdown valves in the broken loops. The reactor

was scrammed on low hot leg pressure at 0.1 secs and the pumps

were tripped at 0.8 secs. (The pumps were not immediately

decoupled from their flywheels as in experiment L2-5, but allowed

to coast down naturally). The pumps coasted down until 16.5 secs.

when their rotational speed fell below the trip point and they

were decoupled from their flywheels. Following the opening of

the blowdown valves the system pressure falls rapidly to the

saturation pressure of the hot leg fluid and voids form in the

upper plenum, core and hot leg. The flow into the core quickly

reverses as a result of the large subcooled critical flow out of

the broken loop cold leg. The core therefore rapidly voids such

that the fuel rods begin to dryout in the centre of the core at

about 0.9 secs. The fuel rod cladding temperatures (recorded by

the thermocouples located on the outside of the cladding) rise as

the energy stored within the U02 is equalised radially across the

whole of the fuel rod. The fuel rod cladding temperatures

continue- to rise until approximately 5 secs when a positive flow

through the core was re-established. This flow through the core

at about 5 secs, occurs as the flow into the vessel downcomer

from the intact loop, which remains almost constant as a result

of the high pump inertia and single-phase nature of the cold leg

fluid, exceeds the falling flow out of the vessel downcomer

through the broken loop cold leg. The broken loop cold leg flow

falls as the system pressure falls from hot leg saturation

pressure to the cold leg saturation pressure. The flow through

the core at 5 secs is enhanced by the flashing of the cold leg

fluid in the vessel lower plenum and downcomer and the intact

loop cold leg. The positive flow through the core cools the core

and produces a rapid quench of the cladding (external)

thermocouples in the lower - 2/3 rds of the central fuel

assembly. After the system pressure falls below the cold leg

saturation pressure the flow of liquid into the downcomer

decreases as the intact loop cold leg voids, so that this flow

quickly falls below that out of the broken loop cold leg, and the

core once again empties. After 1 10 secs therefore the fuel rods

in the core begin to heat up again. A partial top-down quench is

initiated at about 15 secs

AEEW - M 2464 4
and lasts until - 18.5 secs as liquid flowing out of the

pressuriser and along the hot leg into the upper plenum flows

down into the core.

The system pressure falls below the accumulator trip point at

17.5 secs and the ECCS liquid begins to flow into the primary

circuit, the HPIS and LPIS began at 21.8 and 34.8 secs

respectively. The flow out of the broken loop continues to fall

as the primary system pressure falls with no obvious direct

bypass of liquid (ie subcooled liquid in the broken loop cold

leg), except for one slug of liquid between 30 and 32.5 secs.

The lower plenum was estimated to have filled at 30.7 secs

(Ref 1) which is the time that the lowest core thermocouple (ie

at a 2 inch elevation) is observed to quench. This is well in

advance of the time that the accumulator empties. The

accumulator tank for example empties at about 4R secs, while an

additional - 7 secs is required to clear the ECCS line, so that

the ECCS accumulator liquid flow into the intact loop cold leg is

not complete until about 55 secs. Following this the effect of

the accumulator nitrogen flow into the primary circuit is seen as

part of the slug of subcooled liquid, resident in the intact loop

cold leg, is swept out of the broken loop cold leg.

Following the cooling of the fuel rods during the blowdown

period, once the cladding thermocouples dry out they heat up

rapidly in the centre of the core to a temperature of about

800 K, which is close to the corresponding fuel temperature. The

cladding "temperatures then increase slowly as a result of the

fuel decay heat until the bottom of the core begins to quench at

about 31 secs as outlined above. Following this, liquid flows

into the bottom of the core and begins to cool the lower parts of

the fuel rods while the fuel rod quench progresses intermittently

up the bottom part of the core reaching the 21 inch elevation at

about 48-secs. Above the peak power elevation ie at a height of

greater than about 30 inches, the fuel rods do not begin to cool

until about 42 secs at which time the cladding temperatures range

from - 750 K at 31 inches to - 500 K at 62 inches. The quench

time of the fuel rods at these elevations corresponds to the end

of the accumulator liquid flow, with for example times of 54.5

secs at 31 inches, 56 secs at 43.8 inches and 49 inches and 54.5

secs again at 62 inches. (The end of the accumulator liquid flow

into the primary circuit is estimated to occur at about 55 secs -

see above). It is postulated therefore that the flow of

accumulator nitrogen into the intact loop cold leg initates the

flow of a slug of liquid into the core as well as one out of the

broken loop cold leg as described above. The mechanism that

leads to this is described in Ref 13 for example. The flow of

liquid into the core at the time is able to quench the upper

parts of the fuel rods as the majority of the cladding is at a

temperature below the minimum film boiling point of - 650 K. The

quench of the core therefore was complete by 56 secs and occurs

as a direct result of the flow of a slug of liquid into the

bottom of the core driven by the system pressurisation as the

flow into the primary circuit from the accumulator changes from

water to nitrogen.

AEEW - M 2464 5
5(ii) TRAC Calculations

In the following three Sections of the report we present the

results of the four TRAC calculations of experiment LP-02-6

described in Section 3 and-Table 1. Thne results of the four

calculations are presented in the following three groups of

Figures together with the experimental measurements where

appropriate.

GROUP 1, Figure 7 to 77

Calculations (see Section 3 and Table 1)

- "JON'S", "ORIGINAL"

and the experimental data.

GROUP 2, Figures 78 to 148

Calculations; "ORIGINAL", "ZERO-GAP"

and the experimental data.

GROUP 3, Figures 149 to 219

Calculations; "ZERO-GAP", "ISHARP"

and the experimental data.

The results from each of the above groups is described in turn in

the following Sections. In the first Section a detailed

description of the experimental measurements together with a

comparison with the general results of the TRAC calculations is

provided.in addition tq comments on the differences between the

two calculations. The subsequent Sections just review the

differences between the calculations and how these influence the

main elements of the calculated transient.

5(1ii) "JONS" and "ORIGINAL" Calculations

LOOP BEHAVIOUR

These two calculations of the LOFT large break transient

experiment LP-02-6 are identical in the sense that they used

exactly the same input deck. The difference between the two

calculations being that the "JON'S" calculation was performed

using code version X26 (UK version of LANL code version 12.2) and

the "ORIGINAL" calculation was performed using code version B03

(UK version of LANL code version 13.0). There are obviously

likely to be many differences between the two code versions - in

spite of the fact that the code from version 12.1 was formally a

frozen code, however it is thought that none of these changes,

except for one, are likely to have a significant influence on the

behaviour of a large break calculated transient. We consider

AEEW - M 2464 6
that this observation is confirmed by the results presented in

Figures 7 to 77. The one area in which there is a known

difference between the two code versions that is likely to

influence large break-calculations are the changes made the

post-dryout heat.transfer. This accounts for the difference in

the calculated cladding temperatures which occur primarily during

the reflood period. In code version X26 the "error" in the

Forslund-Rohsenow dispersed flow heat transfer coefficient tie

the use of the .liquid thermal conductivity instead of the vapour

conductivity) had been corrected by the UK. In version B03 the

Forslund-Rohsenow relation had been changed by LANL in such away

as to correct the "error" in the value of the thermal

conductivity used but to also increase the numerical coefficient

in order to preserve the resultant value of the heat transfer

coefficient. This revised value of the Forslund-Rohsenow

dispersed flow heat transfer coefficient introduced by LANL in

version 13.0 was kept in the equivalent UK version B03. The

result of this change can be seen as a more rapid cooling of. the

cladding temperatures during reflood with the revised form of the

heat transfer term in the "ORIGINAL" ie B03 calculation.

The first observation from the results of these two calculations

is that their behaviour particularly that reflected by the global

parameters is very similar especially during the blowdown period

(ie 0.0 to 20;0 secs), where the results of the two calculations

are almost indistinguishable. The calculated and experimental

pressure decay, shown for example in Fig 7 for the broken loop

cold leg and Fig 30 for the intact loop hot leg shows a very good

comparison between the two calculations and the experiment, and a

significant improvement over that calculated for LOFT experiment

LP-LB-l (Ref 2). For experiment LP-LB-1 the TRAC calculation

underestimated the primary system pressure after approximately

13 secs. The improvement in the calculation for LP-02-6 is

ascribed to the revised vessel metal heat structures contained

within the LP-02-6 input deck as these produce a significant

increase in the heat released from the vessel metal-work to the

fluid (see Fig 51). There is a small difference in the

calculated system pressure between about 26 and 33 secs, with the

"JON'S" calculation providing a better comparison with the

experimental data. It is-thought that this difference is

possibly due to different condensation rates in the intact loop

cold leg and Fig 20 for example shows that during the approximate

same time period in the "JON'S" calculation a liquid slug forms

upstream of the ECCS injection point whereas one is not formed in

the "ORIGINAL" calculation. Previous experience of large break

TRAC calculations has shown that the details of the intact loop

cold leg behaviour during the accumulator flow period is both

difficult to predict and very sensitive to the details of the

loop and ECCS flows. This of course is always likely to be the

situation when large changes in condensation rates are involved.

The broken loop cold leg density and mass flow shown in Figs 8

and 9 show that although the density is well calculated during

the blowdown period the calculated mass flow is overestimated

both during the subcooled period and during the saturated flow

period when the calculations are approximately 20 kg/sec higher

AEEW - M 2464 7
than the experimental value. This is a consistent feature of all

of the calculated transients, but is different to that of the

LP-LB-l comparison (Ref 2), however that probably just reflects

the difference in the calculated primary system pressures for

LP-LB-1 and LP-02-6 (see above). The.calculated mass flow during

the saturated blowdown period is high in spite of the fact that

a critical flow multiplier of 0.84 is used, a value of 1.0 is

used during the subcooled blowdown. (These numbers were

inherited from LANL and have not been the subject of a study in

the UK, however it would not be possible to justify a number of

less, than 0.84 for the saturated flow period). As observed in

Section 5(i), neither of the calculated transients shows any

direct ECCS bypass, until the accumulator empties at about 53

secs, whereas the experiment shows the flow of two distinct slugs

of subcooled water through the broken loop cold leg (Figs 8, 9,

10) the first betwen 29 and 33 secs and the second between 49.5

and 51.5 secs. Both the calculations and the experiment show the

flow of a slug of subcooled liquid coincident with nitrogen

entering the intact loop cold leg from the accumulator,. however,

the calculated flow is much more extensive than that observed in

the experiment.

Rather surprisingly both of the calculations show some reverse

flow at the measurement location in the broken loop cold leg,

during the bypass phase of the transient. The "JON'S"

calculation shows some reverse flow at - 43 secs while the

"ORIGINAL" calculation shows reverse flow at - 42.5 secs and

46.5 secs, whereas none is observed in the experiment. Given the

good agreement between the calculated and experimental primary

system pressure during this period it is possible that the

reverse flow results from an error in the break pressure used in

the calculation to simulate the presure in the blowdown

suppression tank.

The calculated and experimental intact loop cold leg behaviour is

shown in Figs 20 to 26, the first point to note is the different

pump behaviour as shown in Fig 25. The "ORIGINAL" calculation

used the INEL specified pump inertia and so produces a long coast

down such that the pump is not calculated to decouple from its

flywheel system (ie at a velocity of 75 rads/sec) until after

70 secs, this is consistent with other calculations of the pump

behaviour, see for example Ref 11, Fig 79. The experimental

curve shows a much faster initial rundown of the pump such that

the pump decouples from its flywheel at - 16.5 secs, because of

the subsequent reduced inertia the pump velocity increases during

the bypass phase of the transient as a result of the ECCS related

condensation induced pressure drop across the intact loop. The

main feature of the pump velocity curve for the "JON'S"

calculation is that the pumps-were tripped to decouple from their

flywheels at the experimental time of 16.5 secs. In spite of the

different pump behaviour seen in the two calculations there is

almost no observable difference in the intact loop cold leg flow,

see for example Fig 21 which shows the cold leg mass flow.

The intact loop cold leg calculated and experimental fluid

densities show very good agreement up to - 12.5 secs, both

AEEW - M 2464 8
showing for example the start of the voiding in the cold leg at - 6 secs. Between 12.5 and 20 secs the calculated densities are

slightly higher than the average experimental value, but well

within the range of the experimental error. The calculated

velocity and hence mass flow are- however lower than the

experimental values (by about' 25 kg/sec in the case of the mass

flow) during the first 6 secs when the flow is single-phase

liquid. Following this the experimental fluid velocity and

therefore mass flow falls rather more abruptly than the

calculated values.

Following the initiation of the flow of liquid from the

accumulators into the intact loop cold leg at - 17.5 secs, the

formation of oscillating slugs of subcooled liquid immediately

upstream of the ECCS injection point are observed starting at

about 21 secs. The oscillatory nature of the liquid slugs can be

seen in the measurements of fluid density, mass flow, fluid

velocity and temperature. These observations are consistent with

the behaviour of all of the other LOFT large break experiments,

although as was mentioned in the analysis of experiment LP-LB-l

(Ref 2) a detailed analysis of the individual density and

momentum flux measurements (not shown here) shows that the fluid

flow is unlikely to be one of a simple 1-D slug moving back and

forth along the cold leg pipe. The calculated behaviour is not

one of an oscillatory slug although the calculated fluid

densities, Fig 20, show that in the case of the "JON'S"

calculation there is some intermittent slug flow upstream of the

ECCS injection point but almost none in the case of the

"ORIGINAL" calculation. It is not possible currently to offer an

explanantion for the different behaviours. Both calculations

produce a stable liquid slug downstream of ECCS injection

location.

The broken and intact loop hot leg comparisons are shown in

Figs 14 to 19 and 26 to 32 respectively. The differences in the

behaviour of the two calculations in both the broken loop and

intact loop hot legs is almost negligable. However both

calculations underestimate the broken loop hot leg fluid density

and mass flow after the first few seconds, although the errors on

both measurements are quite large.

The flow in the intact loop hot leg remains in a positive

direction for approximately the first 9 secs as a result of the

pressure drop provided by the slow rundown of the pumps. (This

is in contrast to a positive flow period of approximately

4.5 secs for experiment LP-LB-l where the pumps were decoupled

from their flywheels at the start of the transient). After

9 secs the flow reverses and two peaks in the mass flow are

observed, the first at - 12 secs occurs as liquid flows out of

the pressuriser and back along the hot leg to the upper plenum

and the second at - 16.5 secs when liquid from the upside of the

steam generator tubes flows back along the hot leg. In both of

these instances Fig 27 shows that the magnitude of the reverse

flow peaks is much greater in the calculation than in the

experiment. During the initial (0 to 9 secs) positive flow

period an increase in flow is observed, ie at about 6.5 secs in

the experiment but not in the calculations this attributed

AEEW - M 2464 9
(Ref 1) to be a consequence of the bottom-up flow through the

core at this time. However no significant hot leg flow is

calculated even when the core interface sharpner is turned off - see Section 5(v). As the hot leg side of the reactor drains the

hot leg mass flow falls, and the flow becomes positive again at

about 30 secs. However in the experiment a surge in the hot leg

flow is seen at about 26.5 secs, and several peaks in the flow

are observed between 42 and 51 secs. These later ones presumably

occur as a result of liquid carry over from the core as the lower

part of the core quenches during the period. An increase in the

hot leg flow is seen at - 54 secs in both the experiment and the

calculations coincident with the surge of liquid into the core

following the initial injection of accumulator nitrogen into the

intact loop cold leg.

The depressurisation and water level of the pressuriser is shown

in Figs 31 and 32, the calculated depressurisation rate is

slightly faster than the experimental value as a result of the

underestimation of the initial pressuriser liquid level.

The accumulator level and pressure is shown in Figs 33 and 34,

the agreement between the calculations and the experimental

values is now very good following the renodalisaticn of the ECCS

line (Ref 3). However no explanation can be found for the

discrepancy between the calculated and measured accumulator

pressure during the period when nitrogen flows from the tank.

VESSEL HYDRAULIC AND THERMAL BEHAVIOUR

The vessel hydraulic and thermal behaviour is shown in Figs 35 to

52, while the fuel rod cladding temperatures are shown in Figs 53

to 77. The global vessel behaviour, ie vessel mass, lower plenum

liquid volume fraction etc is shown in Figs 43 to 48, for the two

calculations, there is of course no direct experimental

equivalent data. The results from the two calculations are

virtually identical during the first 20 secs, while after this

there is a slight delay in the filling of the vessel in the

"JON'S" calculation as the ECCS liquid accumulates as a slug in

the intact loop cold leg extending upstream of the injection

point.

The calculated behaviour of the vessel during blowdown shows that

the core, lower plenum and downcomer void during the first 3 to

4 secs as subcooled liquid flows out of the broken loop cold leg.

The core rapidly empties while the lower plenum and downcomer

liquid volume fractions fall to about 0.7. As the flow of

subcooled liquid out of the broken loop cold leg falls it is

exceeded by the flow of liquid into the vessel from the intact

loop cold leg so that the liquid volume fractions of the lower

plenum and downcomer increase. These then fall again after about

6 secs when the flow of liquid into the vessel decreases as the

fluid in the intact loop cold leg flashes. The increase in the

flow of liquid into the vessel produces a flow of liquid into the

bottom of the core beginning at about 4 secs. The flow through

the core is enhanced by the flashing of the liquid in the lower

plenum and downcomer at about 6 secs and then falls to zero again

AEEW - M 2464 10
between about 9 and 10 secs as the lower plenum and downcomer

void. (See Fig 35). In addition to the above flow of liquid

into the bottom of the core a flow of liquid from the upper

plenum down through the core is observed to occur between about

16 and 22 secs. This is shown as a reverseflbw in the core

outlet mass flow, Fig 44.

As stated above, the calculations show that, following the

initiation of the accumulator flow at about 17 secs, the

accumulator liquid flows into and down the vessel downcomer to

fill the vessel lower plenum, and there is no observed direct

bypass of the accumulator liquid out of the broken loop cold leg.

Although of course fluid continues to flow out of the broken loop

cold leg this fluid is saturated and is provided by the flashing

of the liquid in the lower plenum as the pressure falls. The

flow of accumulator liquid into the lower plenum produces an

increase in the liquid volume fraction beginning at about

25 secs. Almost immediately some small quantity of liquid enters

the bottom of the core and its influence can be seen on the

cladding temperature (thermocouples) located at the bottom of the

core. Initially all the accumulator liquid flows down the

downcomer into the lower plenum so that the liquid volume

fraction rises to - 0.75 at about 33 secs. Following this the

liquid flow into the core increases and some liquid begins to

accumulate in the downcomer. At about 40 secs in both

calculations the lower plenum is liquid full and the core liquid

volume fraction is - 0.2. (Note this is still some - 15 secs

before the end of accumulator injection). After 40 secs when the

lower plenum is full the accumulator liquid continues to flow

into the downcomer which therefore rapidly fills, with the

downcomer in the version 13.0 (ie "ORIGINAL") calculation filling

somewhat faster than in the version 12.2 (ie "JON'S")

calculation. The downcomer continues to fill in the calculation

well above the level of the nozzles as a consequence of the fact

that the primary system pressure falls below the boundary

pressure used to model that in the blowdown suppression tank.

The downcomer begins to empty at about 52 to 53 secs which is

coincident with the end of the accumulator liquid flow as the

primary system pressure once more exceeds that at the break.

Following this there is a-rapid increase in the liquid content of

the core.

As stated above there is no detectable difference in the vessel

behaviour between the two calculations during the blowdown

period, and although there are some differences in detail between

the two calculations following the initiation of the accumulator

liquid the global behaviour is the same. The differences in

behaviour almost certainly arise from the extreme sensitivity of

the 1-D condensation model which as we have seen produces an

upstream liquid plug in one instance but not in the other, rather

than a specific difference between the two code versions.

As has been stated in relation to the analysis of other LOFT

large break experiments (see Ref 2), the level and interpretation

of the LOFT vessel instrumentation is both limited and difficult.

However the lower plenum velocity and mommentum flux measurements

(Figs 36 and 42) do confirm the bottom up flow of liquid observed

AEEW - M 2464 11
during blowdown, ie between about 4.5 and 9 secs. Also it is

possible to estimate that the peak velocity and mass flux of the

flow was > 1 m/sec and between 500 and 1000 kg/m*' sec

respectively. The downcomer fluid temperature measurements,

located on the broken loop side, also confirm the broken loop

cold leg measurements in that there was only a small amount of

direct subcooled liquid.bypass. Fig 38 for example shows liquid

subcooling only, between 31 and 33 secs and between 50 and 53

secs, prior to the end of the accumulator liquid injection.

CORE-THERMAL RESPONSE

Central Bundle

The fuel rod cladding temperatures for the "JON'S" and "ORIGINAL"

calculations together with the experiment are shown if Figs 53 to

63 for the central fuel assembly (ie LOFT assembly 5) and in

Figs 64 to 67 for the instrumented peripheral fuel bundles (ie

LOFT fuel assemblies 2, 4 and 6). In addition Table 4 shows the

axial location of the calculational fine mesh together with the

relative power density at the coarse mesh boundaries.

Two features of the calculated temperature transients are

immediately obvious, (1) is the fact that during blowdown (and

therefore for the remainder of the transient) the calculated peak

clad temperatures are more than 100K too high and (2) the fact

that the "ORIGINAL" calculation (version 13.0) cools faster than

the "JON'S" calculation (version 12.2).

The peak clad temperature of a fuel.rod during the initial

blowdown period of a large break transient is determined

primarily by the transfer of heat from the centre of the fuel to

the cladding as the cladding to fluid heat transfer falls

following dryout and as the heat generated within the core falls

to the decay heat level. This means that-the peak cladding

temperature is particularly sensitive to the fuel rod pretransient (steady state) stored energy, ie fuel rod centre

temperature. The only unknown parameter of any significance in

the calculation of t_. z teady state fuel stored energy is the

fuel to cladding heat transfer, ie the fuel-clad gap conductance.

In the TRAC code this is determined from the input value of the

fuel-clad gap width, and in both of these calculations this was

set to the "as manufactured" value of - 100 lons. Because of the

obvious error in the resultant peak clad temperatures

particularly at the bottom of the fuel rods, the influence of

changing the fuel clad gap to fully closed, ie no gap, is

evaluated as part of this sensitivity study (see Section 5.iv).

Calculations of the initial cladding temperature response over

the whole core is made more difficult because of the limitations

of the TRAC fuel pin model, for example there is only a single

fuel pin representation for the whole of the core and for this

pin only a single set of radial dimensions can be input. So that

changes in the pin dimensions both axially and between pins

cannot be modelled. Also changes in the fuel clad gap width and

the fuel and clad dimensions generally, due to mechanical

AEEW - M 2464 12
effects, cannot be modelled, only changes due to thermal effects

are considered.

From Figs 53 and 54 we see that the fuel rod cladding

temperatures during blowdown of the two calculations are -

identical and although there are some small differences in/the

cladding temperatures during the refill period the largest and

most consistent difference is the fact that during reflood the

"ORIGINAL" calculation (version 13.0) cools faster than the

"JON'S" calculation (version 12.2). The major identifiable

difference between the two code versions as was reviewed in

Section 3, is that the dispersed flow (ie void fraction > 0.5)

heat transfer coefficients in the UK version of 13.0 were

significantly higher than those in the TIK version of 12.2. (For

the reasons mentioned in Section 3 the LANL version of both codes

would have given the higher of the two heat transfer

coefficients). The higher heat transfer for the "ORIGINAL", ie

v13.0 calculation would of course produce the observed earlier

cooling of the cladding for identical core fluid conditions.

Although as we see from Fig 48 for example, there are some small

differences in the core liquid mass during reflood, but these on

their own are not enough to be responsible for the different

cladding behaviour.

The experimental cladding temperatures in LOFM are those recorded

by thermocouples attached to the surface of the cladding. This

has lead to intense speculation both to whether they truly

reflect the temperature of the cladding particularly during the

very rapid quench periods and to whether the thermocouples

themselves induce additional cooling that would not be present on

uninstrumented fuel rods. Both of these questions have been

subject to separate effects experimental investigations at both

high and low pressures (Ref 14 and 15). and a review of this

information is currently taking place at AEEW (Ref. 16).

The general response of the calculated and experimental cladding

temperatures during the transient just reflects the, vessel

hydraulic behaviour described above. The cladding temperatures

rise rapidly after about 1 sec as the fuel rods in the central

assembly begin to dry out, increasing to over 1000K after about

3 secs in the experiment at the peak power location. The

calculated peak temperatures are higher by up to lOOK, because of

the too large a value of the steady state stored energy, as

explained above. After approximately 5 secs the surge of liquid

into the bottom of the core produces a rapid cool down (quench)

of the experimentally observed temperatures at all elevations up

to and including the 39 inch level, but not at elevations above

this. In the calculation the cladding is cooled by more than

200K at the 24 and 27 inch elevations, but of course this is not

sufficient to produce a quench. More significant is that in the

calculation the cooling extends all the way to the top of the

fuel assembly so that at the 62 inch elevation for example, where

the temperatures are low because of the lower power, a quench

occurs in the calculation but not in the experiment.

AEEW - M 2464 13
Following the rapid cool down (quench) of the thermocouplecladding in the experiment, dryout occurs again at the centre of

the core after about 11 secs, and the temperature across the the

fuel rod is once again re-equalised as the observed temperatures

rise rapidly to about 800K. This behaviour is confirmed by the

limited fuel rod centre line temperature measurements which show

the centre of the fuel at the 27 inch elevation (Fig 63) to cool

slowly to - 800K at about 15 secs. In the calculated transients

following the blowdown cooling of the fuel rods the cladding

temperatures rise to - 1000K, ie some 200K higher than the

experimental values.

At the higher elevations in the central fuel assembly for the

experiment the influence of the top down flow of liquid from the

upper plenum is seen as the fuel rods quench from the top

downwards between about 15 and 19 seconds. Although a small

downflow of liquid is observed in the calculations (Fig 44)

between 16 and 22 secs. This does not appear to have a major

influence on the cladding temperatures except at the highest

(62 inch) elevation (Fig 62).

Following the blowdown cooling and the re-equalisation of the

fuel rod temperatures, ie after - 15 secs, the cladding

temperatures rise slowly as the core is steam cooled and the

vessel fills with water from the accumulator. This continues

until the first sign of reflood cooling occurs at about 30 secs

which is well before the accumulator empty time of - 54 secs.

The temperature rise turns over at about the same time in both

the experiment and the calculations (particularly the "ORIGINAL"

v13.0 calculation) especially towards the bottom of the core, ie

below - 21 inches. Above this, ie up to 31 inch level the

cooling effect of the core flows is seen in the experiment, but

riot in the calculation until - 40 secs, when as Fig 48 shows

there is an increase in the flow of water into the core. Above

the 31 inch elevation both the experiment and calculations-show a

cooling of the fuel rods after 40 secs. The cooling of the

cladding particularly in the experiment is distinctly oscillatory

in nature, indicating an oscillating flow at the core inlet, this

is likely to arise both as a result of increases in the core

pressure as steam is produced and as a reduction in the pressure

in the intact loop cold leg. as steam condenses on the subcooled

accumulator liquid.

The fuel rod cladding in the central fuel assembly continues to

cool and subsequently quenche, such that, except at the very

bottom of the core,, the quench takes place coherently over

significant lengths of the core. The following for example shows

the quench times at the various elevations in the central

assembly, and we see that

AEEW - M 2464 14
Elevation Quench Time

2" 31 secs

li" 46.7 secs

21" 46.7 secs

24" 54.2 secs

27" 54.2 secs

31" 55.8 secs

43.8" 55.8 secs

49" 55.8 secs

62" 54.6 secs

the core quenches at the 11 and 21 inch elevation at - 47 secs

while the remainder of the core, ie 24 to 62 inches quenches

between 54 and 56 secs. The final core quench (ie between 54 and

56 secs) occurs at the same time as the termination of the

accumulator liquid flow and the initiation of the accumulator

nitrogen flow, and as is explained in Refs 13 and 17 and above

this produces a surge of liquid both out of the broken loop cold

leg and into the core. The coherency of the final quenches

indicate that for this experiment, and for LOFT in general, the

quench process is'dictated by the fluid conditions, rather than

thermal conditions within the fuel rod. In this sense it is

different from the propagating quench fronts observed in slow

forced reflood experiments. The experimental quench temperatures

in this experiment are by and large determined by the fuel rod

temperatures at the time of the "end of accumulator" inflow of

liquid into the core, but are typically less than 700K even at

the peak power elevation. As explained above the relation of the

observed quench temperatures in IOFT to a minimum in the boiling

"Tmin" has been the subject of several separate effects studies,

some of which (Ref 15) have shown that at reflood pressures

(typically - 3 bars) the presence of the external thermocouples

can promote quenches at temperatures higher that "Tmin". The

fuel centre line temperatures (Fig 63) show that in line with the

separate effects studies (Ref 15) that the quench of the external

thermocouples quickly promotes cooling radially across the fuel.

In the calculations the surge of liquid into the core at

54 secs (Fig 48) which results from the termination in the

accumulator liquid flow, produces an increase in the cooling of

the cladding; but because the temperatures are typically 200K too

high at this time and no account of the influence of the external

thermocouples on the quench process is allowed for, the final

calculated quench is delayed by some 40 to 50 secs.

Peripheral Bundles

The fuel rod cladding temperatures for the three LOFT peripheral

instrumented bundles 2, 4 and 6 are shown in Figs 64 to 77.

Fuel assembly 4 is located between the intact loop hot leg and

the broken loop cold leg, fuel assembly 2, between the broken

loop cold leg and the broken loop hot leg and fuel assembly 6

between the broken loop hot leg and the intact loop cold leg,

this arrangement is shown in Fig 6ii. All of the instrumented

rods except one, 4G08-21 (Fig 70), are located on the side of the

AEEW - M 2464 15
peripheral bundles adjacent to the central bundle, whereas rod

4G08 is located towards the middle of assembly 4.

The thermal behaviour of the peripheral bundles, particularly

that of 2 and 6, for the most part just mirrors the behaviour of

the central bundle, except that the temperatures are lower as the

result of the lower power level. The fuel rods dryout as the

core voids during blowdown, reaching a peak temperature of - 900K

at the peak power elevation in all 3 bundles. The bottom-up core

liquid flow produces a rapid cooldown (quench) of all of the

instrumented rods, even at the highest elevation of 49 inches,

between 6 and 8 secs. In bundle 6 the fuel rods dryout again

after about 12 secs rising rapidly to a temperature of - 650K to

700K then more slowly to a peak reflood temperature of - 750K

(Fig 75, rod 6H12-026). In bundle 2 the fuel rods dryout at

about 12 secs, but are then "quenched" again at all but the

bottom elevation from the top-downwards between 14.5 and 18 secs.

These rods then dryout between 18 and 21 secs rising to a peak

temperature of - 700K (rod 2614-011, Fig 64). In fuel assembly

4, Figs 69 to 72, we see that following the blowdown "quenching"

the fuel rods do not immediately dryout again, so that the

resultant reflood peak temperatures are significantly lower, ie

less than 600K. From the instrumented rod located in the middle

of assembly 4 (ie rod 4G08, Fig 70), we see that at this location

the fuel rods do not dryout during the blowdown period. The

lowest elevation on assembly 4 dryout at about 18 secs in line

with the fuel rods in assembly 2, while the higher elevations do

not dryout until about 29 to 30 secs.

Cooling of the rods during reflood begins at about 29 to 30 secs

at the 11 inch elevation (Figs 64, 73) in bundles 2 and 6 and

this is consistent with the temperature measurements for the

central bundle (see previous Section). Following this the

thermocouples show an oscillatory behaviour similar to that

observed in the cetral bundle, and again provide a confirmation

of the likely oscillatory flow conditions at the core inlet. The

cladding temperatures for bundles 2 and 6, during this reflood

period lie between - 600K (2H13-049, Fig 68) and 750K (6H15-026,

Fig 75) and these therefore are the temperatures from which the

fuel rods quench. The quench times for assemblies 2 and 6 are

given belowr these as with the quench of the central fuel

assembly show that the quench (of the thermocouples) is

determined by the fluid conditions rather than the thermal

behaviour of the fuel rods. For example the quenches occur

coherently and are most likely coincident with the flow of liquid

into the bottom of the core. In addition the final quench at the

top of the peripheral fuel rod bundles occurs at - 55 secs, which

again is in line with the data from the central fuel assembly,

and

AEEW - M 2464 16
Height ASSEMBLY 2 ASSEMBLY 6

11 inch 46.7 secs 40.8 secs

21 inch 43.3 secs -

26 inch - 47 secs

30 inch 49 secs 49 secs

39 inch 54.6 secs 54.6 secs

45 inch - 54.6 secs

49 inch 52.5 secs -

results from the surge of liquid into the core following the

change of fluid flow, from the accumulator into the intact loop

cold leg from that of water to nitrogen.

The calculated cladding temperatures for the peripheral bundles

just reflect the general behaviour of those for the central

bundle, ie (1) the blowdown peaks are too high because of the

"high" initial fuel stored energy and (2) the "ORIGINAL" (ie

v13.0) calculation cools quicker during reflood than the "JON'S"

(v12.2) calculation. In addition to these, the first of the

above leads to an overestimation of the cladding temperatures for

bundle 6 during reflood of between 100 and 200K (eg Figs 74 to

77). Finally in bundles 2 and particularly. 4 where in addition

to the experimental bottom-up blowdown quench the fuel rods are

subsequently quenched from the top downwards, the calculated

temperatures which do not show this asymmetric top-down cooling

are some 300K too high.

5(iv) '"ORIGINAL" and "ZERO-GAP" Calculations

The "ZERO-GAP" calculation was the second in the series of TRAC

sensitivities performed as part of the comparison with LOFT

experiment.LP-02-6. This calculation was performed because of

the obvious overestimation of the steady-state fuel stored energy

calculated in the first two calculations when the "as

manufactured" fuel clad gap was used. In the "ZERO-GAP"

calculation the fuel clad gap was set to zero, while in all other

ways the calculation was identical to the "ORIGINAL" calculation

(ie it used code version B03, the UK version of LANL code version

13.0). As would be expected the major effect of the above change

is to the calculated core cladding temperatures, however it might

be anticipated that this change could influence the heat

transferred to the fluid and hence the hydraulic behaviour.

The improvement in the calculated cladding temperatures during

blowdown for the "ZERO-GAP" calculation can be easily seen in

Figs 124 etc for the central fuel bundle, and Figs 136 etc for

the peripheral bundles. However one consequence of reducing the

fuel clad gap over the whole length of the fuel rod, As is

required by the TRAC simplified fuel rod model, is that the peak

temperature during blowdown at the top of the core is now

underestimated. This can be seen particularly in the central

fuel bundle at all elevations above about 40 inches.

Note Comparisons of the TRAC calculations with the experimental

results for the peripheral bundles is made difficult in

AEEW - M 2464 17
some instances because of an error in the TRAC (v13.0) hent

transfer logic that artificially quenches some rods during

the blowdown period (Ref 18), see for example Fig 146.

An improved fit to the overall blowdown temperatures could

obviously be made by adjusting the fuel clad gap along the length

of the fuel rods, ie a closed up gap at the bottom and a

partially open one at the top. However for this to be more than

just a "fitting" exercise additional information ought to be

available either from fuel PIE or a fuels code.

In the centre of the core, eg Figs 127, 128, where the "ZERO-GAP"

blowdown peak temperatures are now well-represented, the

calculated temperatures fall to - 800K as a result of the bottomup core cooling, and subsequently rise to about 850K as the

cooling diminishes and the temperatures across the fuel rod

equalise out. In the experiment the recorded temperatures on the

external thermocouples cool down rapidly to the saturation

temperature as a consequence of the bottom-up liquid flow, but

then rise to - 800K as the cooling diminishes and the

temperatures across the rod re-equalise. The average rod

temperature therefore after the blowdown cooling is only some 5ON

higher in the "ZERO-GAP" calculation than in the experiment.

This shows therefore that at this elevation the net heat transfer

from the cladding. to the coolant is only marginally smaller in

the case of TRAC compared to the experiment. The difference in

the net cooldown of the fuel rod could therefore be wellaccommodated within the uncertainty of the inlet fluid

conditions, without requiring major changes to the TRAC heat

transfer package. The above observations also apply in general

to the lower core elevations, although the difference between the

TRAC "ZERO-GAP" and experiment clad temperatures after the end of

the blowdown cooling are in some instances somewhat higher.

In the upper part of the central fuel bundle and generally across

the peripheral bundles, differences between-the calculated and

experimental fluid conditions make comparisons more difficult.

At the 43.8 inch elevation (Fig 131) for example, we see that

(1) The calculated cladding temperature shows dryout well in

advance of the experiment.

(2) As mentioned above the "ZERO-GAP" calculated peak clad

temperature is lower than the measured value (assumed to be

due to a partially open gap towards the top of the core).

(3) In the experiment the bottom-up liquid flow is limited so

that the temperature of thermocouple does not fall to

saturation, whereas in the calculation more extensive

cooling is observed, and finally;

(4) The rod thermocouple cools to saturation at - 19 secs due

to the top-down flow of liquid from the upper plenum and

this is not predicted in either calculation except at the

highest elevation (ie at 62 inches, see Fig 133).

AEEW - M 2464 is
As stated above differences 1, 3 and 4 arise because of

inaccuracies in the calculated core blowdown fluid.conditions and

the sensitivity of the thermal response to them, and for this

reason it is not easy to see how to improve the accuracy of the

calculation. However it does go to show that an accurate

calculation of the core blowdown hydraulics is a pre-requisit to

the calculation of the core blowdown cooling.

As a full review of the loop and vessel behaviour is contained in

the previous Section we only comment here on the observed

differences between the two calculations and their relation to

the experimental data. As might be expected there are only minor

differences in both the loop and vessel hydraulic conditions

between the "ORIGINAL" and "ZERO-GAP" calculations. In line with

the comments in the previous Section-we see that neither

calculation produces any direct bypass of subcooled ECCS liquid,

whereas the experiment shows subcooled bypass at - 31 secs,

estimated to be between 80 and 130 kg. The calculated broken

loop mass flow (Fig 80) also shows that there is no reverse flow,

ie flow from the BST to the reactor vessel in the "ZERO-GAP"

calculation, as there is in the "ORIGINAL" calculation between

42 and 48 secs. This results from the fact that the system

pressure is fractionally higher in the "ZERO-GAP" calculation due

to the increased heat transfer from the core fuel rods to the

coolant.

The calculated intact loop cold leg behaviour during refill, as

explained in the previous Section, is very sensitive to the

details of the calculated transient particularly through the

condensation model and this can then feed back and influence the

vessel refill and early core reflood behaviour. Figs 91 and 92

which show the intact loop cold leg density and mass flow,

upstream of the ECCS injection point, show that there is a

difference in the behaviour of the two calculations during the

refill (accumulator flow) period, with the "ZERO-GAP" calculation

producing some rapid liquid slugs after - 38 secs. This movement

and accumulation of the.ECCS liquid in the intact loop cold leg,

through the behaviour of the condensation model, then modifies

the subsequent core reflood. An additional consequence of the

different intact loop cold leg behaviour is that the pump in the

"ZERO-GAP" calculation runs down slightly quicker after

45 secs, (Fig 96).

One interesting feature of both the calculation and the

experiment observed in the intact loop cold leg is that following

the exhaustion of the nitrogen from the accumulators, the liquid

begins to accumulate, producing an increase in the intact loop

cold leg density, (Fig 91), at about 85 secs.

Finally the other observable difference between the two

calculations, is that following the end of the accumulator liquid

flow, the pressure drop from the reactor vessel to the BST

produced by the flow of nitrogen steam and water is smaller in

the "ZERO-GAP" calculation than in the "ORIGINAL" calculation.

So that after 55 secs the system pressure (see Fig 114 for

example) is lower in the "ZERO-GAP" calculation. Fig 114 however

AEEW - M 2464 19
also shows that it is now closer to the experimental value. The

difference in this pressure rise results from the different mass

flow and densities calculated along the broken loop cold leg

(Figs 80 and 79) after 55 secs, and these differences result from

the way liquid has accumulated in the intact and broken loop cold

legs and along the top of the downcomer prior to this time.

5(v) "ZERO-GAP" and "ISHARP" Calculations

The fourth TRAC-PFl/MOD1 calculation ("ISHARP") of experiment

LP-02-6 performed was a repeat of the previous "ZERO-GAP"

calculation (code version UK B03, LANL 13.0) except that the core

interface sharpener logic was bypassed. The reason for carrying

out this calculation was to examine the effect of bypassing this

logic in an integral calculation. Previous analysis of separate

effects reflood experiments (Ref 7) had recommended bypassing

this logic as the best way of modelling the core void fraction

above the quench front and previous plant studies had also shown

that the interface sharpener logic could produce unphysical

liquid holdup in the core during blowdown. As the differences

between the "ZERO-GAP" and "ISHARP" calculations relate to the

core hydraulics, one would expect to see differences primarily in

the core flows and from these differences in the fuel rod

cladding temperatures, and possibly via the heat input to the

fluid from the fuel rods, differences in the loop behaviour.

The results from the two calculations together with the

experimental data, where appropriate are shown in Figs 149 to

219. The most striking feature of the comparison taken as a

whole is that the difference between the two calculations is

relatively small. The resultant cladding temperatures for

example (Figs 195 to 219) are very similar, this just amplifies

the fact that for large break transients performed in LOFT

(primarily because of the size and location of the core) the

cooling of the fuel rods during both blowdown and reflood is

dictated by the system hydraulics in the loops and the vessel

downcomer.

It should be noted, that as for the previous calculations

performed with code verison 13.0, the "ISHARP" calculated

cladding temperatures are subject to the error in the heat

transfer logic (Ref 18) described in the previous Section. (See

for example Figs 195, 206, 207, 212, 213 and 217).

The core inlet and outlet flows together with the core liquid

mass (Figs 185, 186 and 189), show for the ISHARP calculation, as

would be expected, that during blowdot-ni more of the liquid

flowing into the bottom of the core flow out of the top and so

less accumulates in the core. After the flow into the core

during blowdown, liquid re-enters the core just after 30 secs in

both calculations, as the lower plenum fills. After - 40 secs

the core flow oscillations for the "ISHARP" calculation increase

in magnitude with the liquid fraction (Fig 190) oscillating

between - 0.2 and zero, this is also reflected in the behaviour

of the downcomer and lower plenum volume fractions (Figs 189 and

188), so that the average quantity of liquid in the core after

AEEW - M 2464 20
40 secs is slightly less for the "ISHARP" calculation. Following

the end of the accumulator liquid flow at - 54 secs the surge of

liquid into the core occurs in both calculations, only the

absence of the interface sharpener logic in the "ISHARP"

calculation allows more of the liquid to flow out of the top of

the core and so the mass of liquid retained in the core is

slightly less. Also the subsequent oscillations in the core

liquid content that result from the fuel rods quenching are

greater in magnitude for the "ISHARP" calculation.

As stated above, the above differences in the core hydraulics

produce only small changes to the cladding temperatures. At the

peak power elevation of the central fuel assembly, Figs 197 to

200, we see that during blowdown the "ISHARP" transient cools

somewhat quicker following the bottom-up flow of liquid as liquid

flows through the core rather than being retained at the bottom.

However the period of cooling is slightly shorter so that the net

heat loss from the fuel rod to the coolant is about the same. So

that following the blowdown cooling the calculated cladding

temperatures in the centre of the core rise to about the same

value, ie - 50K higher than those in the experiment. If anything

the "ISHARP" calculated blowdown temperature transient is in

close agreement with the experimental data.

At these elevations (ie 20 to 30 inches) reflood cooling in the

calculations begins just prior to 40 secs and although the

cladding temperatures level off they do not fall (in the "ISFAPP"

calculation) until after the "post accumulator" flow of liquid

into the -core at - 54 secs. This just reflects the slightly

lower average core liquid content in the "ISHARP" calculation

during this period. However following 54 secs the cooling is

such that both calculations have near identical quench times.

At the bottom of the central fuel assembly (Figs 195 and 196) the

initial dryout of the "ISHARP" calculated fuel rod is delayed,

due in part to the heat transfer error described above, so that

the resultant cladding temperatures during blowdown are lower

than both the "ZERO-GAP" calculation and the experiment. Towards

the top of the core (Figs 201 to 204) the overcooling and

resultant quenching of the fuel rods due to the bottom-up flow of

liquid is even more exaggerated for the "ISHARP" calculation (see

Fig 203) and although some influence of the top-down flow of

liquid is seen this is not enough to extend the area of quenching

below that resulting from the bottom-up liquid flow.

A comparison between the two calculated cladding temperature

transients for the peripheral fuel bundles is made almost

impossible because of the error in the heat transfer logic

described above and in Ref 18. The spurious cooling produced by

this error which is restricted to high void fractions is more

prevalent in the "ISHARP" calculation than in the other 13.0

calculations because of the changed core hydraulic conditions.

The changes in the loop flows produced by the change in the core

hydraulic modelling are very small. As a result of the slightly

AEEW - M 2464 21
lower quantity of heat transferred from the core to the coolant

during the early part of reflood the system pressure falls just

below that used to represent the BST, so that liquid flows back

along the broken loop cold leg at - 48 secs. As a consequence of

the increased flow out of the top of the core during blowdown for

the "ISHARP" calculation one might expect to see a change in the

"Intact and broken loop hot leg flows, and although a small

increase in the broken loop hot leg flow is seen (Fig 158) at - 9.5 secs the change is very small.

As might be expected there are some changes to the intact loop

cold leg behaviour during reflood (Figs 162, 163) but again these

are small and the flow of liquid up-stream of the ECCS injection

point is limited to a short period of between - 38 to 48 secs for

both the "ISHARP" and "ZERO-GAP" calculations. These cold leg

flow oscillations occur either in part or whole as a consequence

of the pressure induced oscillations in the core flow rather than

being induced by changes in the cold leg condensation. This

contrasts with the experimentally observed intact loop cold leg

flow oscillations which extend for most of the accumulator flow

period, ie from - 21 to 54.5 secs, and must arise at least

initially from the condensation of the intact loop steam flow by

the subcooled ECCS liquid.

6 SUMMARY AND CONCLUSIONS

This report compares the results of four TRAC-PFl/MOD1

calculations with the experimental data for the LOFT large break

experiment LP-02-6. The four calculations compare changes to;

code version, ie versions 12.2 and 13.0, fuel pin modelling, ie "as manufactured" and zero steady state fuel clad gap and to core

hydraulic modelling, ie with and without the core interface

sharpener logic.

The features that distinguish the LOFT LP-02-6 experiment from

the previous 200% double-ended cold leg break experiments L2-3

and L2-5 and the subsequent experiment LP-LB-l were the fact that

it was performed at near full power (ie 47 MW) with a relatively

low loop flow (248 kg/sec) and therefore a high core AT and the

fact that the pumps were tripped and allowed to coast down

naturally at the start of the transient. This contrasts with

L2-3 where the pumps were kept running and L2-5 and LP-LB-1 where

the pumps were decoupled from their flywheels at the start of the

transient.

The transient was initiated at time zero by the opening of the

quick acting blowdown refief valves, and the upper plenum and

core rapidly void as subcooled liquid flows out of the broken

loop cold leg. As the core voids the reactor power falls and the

fuel rods dry out. The cladding temperatures rise as the stored

energy in the fuel equalises out across the fuel pin. The

subsequent behaviour of the fuel rods during blowdown in LP-02-6

is dictated by the core hydraulics as for the other LOFT large

break experiments. The balance of liquid flow into the vessel

downcomer is such that after - 4 secs there is a net inflow as

the broken loop cold leg flow falls, as the system pressure falls

AEEW - M 2464 22
to the 'cold leg' saturation pressure, and the inertia of the

pumps produce a flow of liquid along the intact loop cold leg

close to the steady state value. The net inflow into the vessel

produces a small bottom-up core flow which is enhanced by the

flashing of the cold liquid in lower plenum and downcomer. The

core flow primarily cools the lower 2/3 rds of the fuel rods - to

the extent that the recorded temperatures on the external

thermocouples fall to saturation. However in addition to the

bottom-up flow there is a significant downflow at about 15 secs,

as liquid flowing back along the intact loop hot leg from the

pressuriser and the up (hot) side of the steam generator tubes

accumulates in the upper plenum. This downflow is sufficient to

cool the external thermocouples to saturation at all elevations

from the top of the core down to about 30 inches. Therefore the

whole of the core is subjected to blowdown cooling either from

the bottom-up flow or the top-down flow and the central region

from - 30 to 40 inches experiences both. This "double" cooling

is unique to experiment LP-02-6 and reduces significantly the

core stored energy.

There has been considerable speculation as to whether the

observed LOFT fuel rod behaviour is indicative of what is

happening on the unistrumented fuel rods, and this is currently

the subject of a separate investigation. However an indication

of the heat removed from the instrumented fuel rods can be

obtained from the thermocouple temperatures flowing the blowdown

cooling, when the fuel rod temperatures are once again

re-equalised. At the peak power elevations, ie between about 24

and 30 inches the cladding temperature rises to - BOOK.

The primary system pressure falls to the accumulator trip point

of 42 bars (600 psi) at about 17.5 secs and accumulator liquid

begins to flow into the intact loop cold leg. In line with all

the other LOFT large break experiments the measurement rake

immediately upstream of the ECCS injection location indicates an

oscillatory flow of subcooled liquid along the intact loop cold

leg starting at about 21 secs. This flow continues until the

flow of accumulator liquid into the intact loop cold leg

terminates at - 54 secs. The accumulator liquid flows into and

down the downcomer filling the lower plenum. The broken loop

cold leg measurements supported by the downcomer measurements

located on the broken loop side show that there is no continuous

bypass of subcooled liquid. However a slug of subcooled liquid

is-observed to flow along the'broken loop cold leg between - 29

and 32 secs, the total mass of this slug is estimated to be very

roughly about 100 kg; compared to the total accumulator volume of

1.69 m , ie - 1,690 kg. An additional slug of subcooled liquid

flows along the broken loop cold leg at - 50 secs, again with a

total mass of roughly 100 to 150 kg. Because of the small scale

of the LOFT facility and therefore the relatively high metal-work

heat flux the primary system pressure never falls below that in

the BST. So that in addition to the flow of the two slugs of

subcooled liquid along the broken loop cold leg there is a flow

of two-phase saturated fluid as the liquid in the lower plenum

continues to flash and steam and entrained liquid flow from the

vessel to the BST.

AEEW - M 2464 23
The lower plenum fills rapidly with ECCS liquid so that the

bottom of the core begins to cool again at - 31 secs. Following

this time cooling is observed progressively up the core with a

turnover, in the cladding temperature rise above 30 inches

occurring at about 40 secs. The most noticeable effect observed

by the cladding-thermocouples once reflood cooling starts is that

they behave in an oscillatory manner. This is.attributed to an

oscillatory core flow which is likely to occur as a result of a

combination of core-steam generation oscillations and intact loop

cold leg condensation induced oscillations. Just as the core

inlet hydraulics determines the fuel rod cooling it also

determines the fuel rod quench. Except at the very bottom of the

core a significant degree of coherency is seen in the fuel rod

quench, for example in the central fuel assembly the 11 inch and

21 inch thermocouples and some of the 15 inch thermocouples all

quench at - 46.7 secs, and above 24 inches the final quench

occurs between 54 and 56 secs. The final quench coincides with

the termination of the accumulator liquid flow, and results from

a surge of liquid into the core as the reduction in condensation

and the presence of the accumulator nitrogen causes the intact

loop cold leg pressure to rise. The rise in the intact loop cold

leg pressure also causes some of the ECCS liquid located in the

intact loop cold leg and at the top of the downcomer to flow out

of the broken loop cold leg to the BST. Because of the blowdown

cooling of the core the maximum cladding temperature at - 54 secs

when the surge of liquid into the core occurs is only - 700K, so

that the whole of the core in experiment LP-02-6 is cooled and

quenched by the liquid from the accumulator.

The results from the four TRAC-PFl/MODl calculations bear a large

degree of similarity particulary in their hydraulic behaviour.

They all therefore, in the main, produce the same global

transient and suffer from the same modelling deficiencies. Those

sensitivities performed for a specific reason, eg reducing the

steady state fuel clad gap obviously produced the desired result

of lower, cladding temperatures.

In spite of the fact that the calculated transients overestimate

the observed subcooled flow in the broken loop cold leg, flow

into the core after - 4 secs extends to the top of the core and

quenches the 62 inch elevation whereas in the experiment the

"quench" only reaches the 45 inch level. However whereas in the

experiment the subsequent top-down liquid flow "quenches" the top

of the core particulary in the peripheral fuel bundles no such

cooling is observed in the calculations. Therefore particularly

towards the top and the bottom of the core the calculated fuel

rod temperatures after blowdown are higher than the experimental

values. In the centre of the core however (ie - 24 to 27 inches)

for the "ZERO-GAP" calculations the calculated cladding

temperatures are only about 50K too high showing that the net

heat loss from the fuel rod for the calculations is only slightly

lower than in the experiment.

In all four calculations there is no direct bypass of the ECCS

subcooled liquid so that, as in the experiment, the lower plenum

fills up rapidly with some liquid first entering the bottom of

AEEW - M 2464 24
the core at - 28 secs. The subsequent core inlet flow is

oscillatory as a result of steam production in the core, and the

fuel rods begin to cool at - 32 secs at 11 inches and at - 39 secs at 21 inches.

One region where there is a difference in the behaviour of the

four calculations is in the intact loop cold leg during the

accumulator liquid flow period. In some cases liquid slugs form

upstream of the ECCS injection point and in other cases not.

These differences are attributed to the sensitivity of the TRAC

condensation model to small changes in the steam and liquid flows

rather than to any specific modelling changes between the four

calculations. In none of the calculations however was the

calculated flow similar to the experimental observations, and

because no bypass was calculated the differences in the

calculated intact loop cold leg behaviour only had a very minor

effect on the vessel refill and subsequent core reflood.

In all of the calculations a surge of liquid into the core occurs

as a result of the pressurisation of the intact loop cold leg as

the flow from the accumulator changes from subcooled water to

nitrogen. This liquid surge effectively fills the small LOFT

core and so the fuel rods cool. The final quench is delayed

because the cladding temperatures are at least 80 to 100K higher

than the equivalent experimental values and no modelling of the

influence of the external thermocouples on the quench process is

included in the calculations.

One may Conclude therefore that although small variations were

observed in the hydraulic behaviour of the four calculations,

because no changes were made'to the following sensitive areas the

general behaviour of all the calculations was the same; ie the

nature. of a LOFT transient is determined by:

- the blowdown cooling, in which the calculations show too

-much bottom-up flow and not enought top-down.

- ECCS bypass, none is calculated and only small slugs of

direct bypass are observed in the experiment.

- the slug of liquid forced into the core following the

termination of the accumulator liquid flow, which is

sufficient to cool/quench the whole of the "short" LOFT

core.

The thermal response of the core to the above hydraulics is of

course different for the different calculations, with those

calculations with the reduced fuel stored energy (ie zero fuel

clad gap) producing results closest to the experiment. However

the very limited fuel pin model available in TRAC restricts the

modelling ability to better simulate the observed thermocouple

behaviour.

7 ACKNOWLEDGEMENTS

The authors wish to acknowledge the valuable assistance of

Dr J Birchley who adapted and modified the TRAC input deck for

AEEW - M 2464 25
LOFT from that used in the previous analysis of experiment

LP-LB-l and who performed the first of the calculations analysed

in the report.

8 REFERENCES

(1) J P Adams, K G Condie,-D L Blatt. Quick-Look Report on

OECD LOFT Experiment LP-02-6. OECD LOFT-T-3404,

October 1983.

(2) P Coddington. Analysis of LOFT Experiment LP-LB-1 Using

the TRAC-PFl/MODl Code. UKAEA Internal Publication.

(3) J Birchley. Modifications to the TRAC-PFl/MODl Input

Models for LOFT. UKAEA Internal Publication, March 1986.

(4) M Blackmore, J Birchley. Modelling of LOFT ECC Injection

Line for TRAC-PFl/MODI. UKAEA Internal Publication, May

1986.

(5) J Birchley. Heat Structures for the 3-D Vessel

Representation of LOFT with TRAC-PFl/MODI. UKAEA Internal

Publication.

(6) J Birchley, P Coddington. Post'Experimental Analysis of

OECD-LOFT Experiment LP-02-6 with TRAC-PFI/MODI. To be

published.

(7) R O'Mahoney. A Study of the.Reflood Characteristics of

TRAC-PFl/MODl. AEEW - M 2305, April 1986.

(8) E M Feldman. OECD LOFT Project Experiment Specification

Document, Cold Leg Break Experiment LP-02-6.

OECD LOFT-T-3402, July 1983.

(9) Private Communication. Letter: P Coddington to

Salih Guntay, EIR Switzerland, .July 1987.

(10) TRAC-PD2 Independent Assessment.

NUREG/CR-3866, LA-10166-MS, December 1984. Pages 234 to

291.

(11) T D Knight. TRAC Analysis of LOFT LP-02-6. LA-UR-85-3723,

October 1985.

(12) A B Wahba. Emergency Core Coolant Systems and Their

Effectiveness in Large Break LOCA.

Paper presented to the OECD-LOFT Specialist Meeting on

Large Break LOCA, 24-27 March 1987, Grindelwald,

Switzerland.

(13) P Coddington. Comments on the Accumulator Nitrogen

Injection Phase of a Large Cold Leg Break PWR

Loss-of-Coolant Accident. UKAEA Internal Publication,

August 1986.

(14) S N Aksan. Evaluation of Analytical Capability to Predict

Cladding Quench. EGG-LOFT-5555, August 1982..

AEEW - M 2464 26
and

R C Gottula. Effects of Cladding Surface Thermocouples and

Electrical Heater Rod Design on Quench Behaviour.

NUREG/CR-2691, February 1984.

(15) S Yanar, S Guntay. Effect of External Thermocouples on

Quench Temperatures Evidence From NEPTUN Reflooding

Experiments. Paper presented at the OECD-LOFT Specialist

Meeting on Large Break LOCA, Grindelwald, Switzerland.

24-27 March 1987.

G Class et al. Measurement of Cladding Temperatures with

Loss-of-Fluid-Test Thermocouples in the COSIMA Blowdown

Test Facility. Nuclear Technology, Vol 69 (April 1985)

p 72.

and

G L Shires et al. An Experimental Study of the Effect of

External Thermocouples on Rewetting During Reflood.

AEEW - R 1357.

(16) R O'Mahoney, C Gill, P Coddington. Status of the High and

Low Pressure Quenching Studies at AEEW, Spetember 1987.

UKAEA Internal Publication.

(17) P Coddington; The Effect of Accumulator Nitrogen on the

Reflood of a PWR Core During a Large Break LOCA.

Paper presented to the IAEA Specialist Meeting on 'Fuel

Behaviour Under Accident Conditions and Acceptance

Creiteria, 30 September-4 October 1985, Warsaw, Poland.

(18) Private Communication. Letters: P Coddington to R Jenks,

LANL, USA. 29 January 1987, and 7 and 24 April 1987.

AEEW - M 2464 27

TABLE 1

TRAC CALCULATIONS

NO

1

2

3

4

LABEL

"JONSq"

"ORIGINAL"

"ZERO-GAP"

"ISHARP"

CODE VERSION

LANL UK

12.2 X26

13.0 B03

13.0 B03

13.0 B03

FUEL CLAD

GAP WIDTH

100 ,.on

100 ilon

0.0

0.0

INTERFACE

SHARPENER

LOGIC

Yes

Yes

Yes

No

AEEW - M 2464

29
- TABLE 2

INITIAL CONDITIONS FOR EXPERIMENT LP-02-6

TRAC "

Parameter

Primary Coolant System

Temperature across core (K)

Hot leg pressure (MPa)

Cold leg temperature (K)

Mass flow rate (Kg/s)

Primary coolant pump injection

(both pumps) (I/s)

Core bypass pipe flow (Kg/s)

Hot leg nozzles bypass flow (Kg/s)

Reflood assist valve flow

rate (Kg/s)

Total core bypass flow (Kg/s)

Reactor Vessel

Power level (MW)

Maximum linear heat generation

rate (KW/ft)

Calcu-iatid Experimental

Value Value

34.5

15.04

556.7

248.1

0.0

6.5

5.6

13.1

25.2

33.1±1.4

15.09±0.08

555.9±1.1

248.7±2.6

0.092±0.003

i

I

j Not.

measured

I directly.

I

I

47.0

15.07

(Av rods)

16.20

(Peak rods)

46.0±1.2

14.9±1.1

Steam generator secondary side

Pressure (MPa)

Steam generator feedwater flow

rate (Kg/s)

5.62

2.53

Pressuriser

Liquid volume (m3 )

Steam volume (m3 )

0.555

0.376

0.607±0.02

0.39±0.02

AEEW - M 2464

30
Water temperature (K)

Pressure (MPa)

Liquid level (m)

TABLE 2 (Continued)

615.4

15.03

1.26

615.615.8

15.3±0.11

1.04±0.04

Broken Loop

Cold leg temperature (K)

Hot leg temperature (K)

Reflood assist valve leak flow

rate (Kg/s)

Suppression Tank

Pressure (gas space) (KPa)

Emergency Core Cooling System

Accumulator liquid level (m)

Accumulator liquid volume (m,3 )

Accumulator gas volume (m3 )

Accumulator pressure (MPa)

Accumulator liquid temperature

High pressure injection flow

rate (2/s)

High pressure injection liquid

temperature (K-)

Low pressure injection flow

Rate (1)

Low pressure injection liquid

temperature (K)

556.7

556.1

13.1

553±6

560±6

15.04

1.05

1.315

(tank)

0.36

(line)

0.642

4.11

(K) 302.0

1.50

302.1

1.2360

0.4559

0.9506

4.11±0.06

302±6.1

1.04±0.04

305±7

5.5

302.9 305±7

AEEW - M 2464

31
TABLE 3

CHRONOLOGY OF EVENTS FOR EXPERIMENT LP-02-6

Event TRAC

Cal cu-lated

Value

Experimental

Value

Blowdown valves opened

End of sub-cooled blowdown

Reactor scrammed

Primary coolant pumps tripped

Cladding temperatures initially

deviated from saturation

End of sub-cooled break flow

Maximum cladding temperature

(1061 K @ 24 in) reached

(blowdown)

Bottom-up core rewet initiated

Bottom-up core rewet complete

Partial core top-down quench

initiated

Pressuriser emptied

Primary coolant pumps disconnected

from flywheels

Accumulator injection initiated

Partial core top-down quench complete

High pressure injection initiated

Lower plenum refill complete

(from void)

Lower plenum refill complete

(thermocouple)

Low pressure injection initiated

0.0

0.05

0.8

0.32

4.9

4.6

4.2

13.1

13.6

16.6

22.0

36.5 to 48.2)

1

28.7

35.1

0

0.05t-.05

0..1±0.01

0.8±0.01

0.9±0.01

4.0_±0.5

4.9±0.2

5.2 ±0.2

9.-1±0.2

14.8±0.02

15.5±0.5

16.5 ±0.01

17.5±0.5

.18.6±0.2

21.8±0.01

30.7±0.2

34.8 ±0.01

AEEW - M 2464

32
TABLE 3 (Continued)

Maximum cladding temperature

(929.7 K @ 24 in) reached (reflood)

Accumulator empty

40.5

48.0

53.0

91.1

.-- 41±0.2

Accumulator injection complete

Core quench complete 56±0.2

a Ref 1 calculates the accumulator injection complete time by

extrapolating from the time the accumulator is empty to the

time the connecting piping is empty assuming a constant mass

flow

AEEW - M 2464

33
TABLE 4 .°

CORE AXIAL FINE MESH ELEVATIONS AND RELATIVE POWER

DENSITY

Fir e Height Power Dens

Mes

ity

;h

* 1

2

3

4

5

6

7

8

* 9

10

11

12

* 13

14

15

16

17

18

19

20

.21

Metres

0.0

0.07625

0.1525

0.22875

0.305

0.362

0.419

0.476

0.533

0.59025

0.6475

0.70475

0;762

0.87625

0.9905

1.10475

1.219

1.33325

1.4475

1.56175

1.676

Inches

0.0

3.0

6.0

9.0

12.0

14.25

16.50

18.75

21-.00

23.25

25.50

27.75

30.00

34.5

39.0

43.5

48.0

52.5

57.0

61.5

66.0

0.59415

1.35550

1.54060

1.47230

0.78851

0.029708

* Fluid dynamic cell boundaries

AEEW - M 2464

34
t13

INTACT LOOP BROKEN LOOP

XBL-1 EXPERIMENTAL QUICK OPENING

o•• • ~STATION MEASUREMENT ••• VALVE 121

r STEAM

GENERATOR

S PC-2 SIMULATOR

SEXPERIMENTAL BREAK

MEASIUEMET STTIO MEASPRSSIOMENR

GENERATOR STATIPN f -•'ISOLATION

%. • VALVE (2)

BREAK PLANE..

.... MOMOET OFBL-2 EXPERIMENTAL

"•'i• "" ~~PUMP SIMULATOR AUREN

i -,,'', • i ECC LOCATION INJECTION

PRESURIER PPS C-1EXPERIMENTA L

STATION

' REACTOR

PC-3 EXPERIMENTAL VESSEL

,/'- LOWER

PLENUM

REACTOR VESSEL

FIG.1. MAJOR COMPONENTS OF LOFT SYSTEM ,
thi XORIOWAXRil

STORAGE VAlpI XRO-69

ACCUV~t AIDA LPIS

a "PIS & PUHPS

t'J ,PU 'P!1| ME 4- Al'Ll.S,.C.D.,F IPISliA!GRB •O[[ONTAMILAtlEI .

OPup'& ,IIIC- ' l(i AT' 

,•AUXILIARY If ft-PC- lilt 1A.8,1 TI.et-IA,e,c SUMP uliP

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FUR ,.N I-PC A I VAV AND MECHANICALt

$YSEMA PP1Is.& to INIAO

So -VAl.o 1 VASM UP .

I. 1 .i.C A8 ECT. Nf 1SlOWDOWNN

(V POle hA FOR P ANP AP LOCATIONS

n --. -OECTION-L P IENJO I ATFOO ALIIS I(IPOINT

BYPSS SYSE Ut[A

IS:"P(POL DION TAL#

II. AXERMU A.s LOO STALO1DOWN

CI-Ai(SUP

P.. COREAI

if Pil-l IE-C*IS, CUTPPERYT

ACTI UIUt.~

FLOOD ASSIST Nu,•t• TomEXANIO

CYCLIN t ___ :PASS SYSTEM s'iON / B!, P VA•LVEt T-PISOtA -ION JOINr P

A( PUMP A

I A,, IT I S_ STtv[ [Cn-1/ a\.1

It. AI.n

PRIMARY COOLAN Coto P " *IOE A J, lOOP 9"CDE, i R lA -IP ioIs~OV

PU-MP PP IN -29.2E "-$N PINTNEO- P'- tel I I LINE ED• I.... ,, I i

P[-PC-O*'l S'T7 ,o SU• tSSoo r• :- ' SIO fi I-''

PIP-?OT IItiSHEAI WITH INTU 5 ETT ON

; * tfCt*Il(mttY P1- C"I.I9 CO.1 ." IO II

I[LI[(DPIRICA.C $D T SPR SIN• J • • L I UI|$O

Pf-PirI& 1qPA 0121C A it10P-1ASIO I t ,. 1 ' -- / , i t T A N •~ s s

It114t R,1 (.•,'T.I.tON'i .'1-'mi'•1 1 '1 UIISIAIOMf-P|,,

ACCUMULATOR ji~~~~pillO* 1, f.`1-11 F.,1-1

FI5.2. ~ ~ ~ ~ ~ IHINTUET ~~ tI TIO"OTPPNCAHMTI 
STEAM PRESSURIZER

GENERATOR

6 EI- COMPONENT NUMBERS

a6'

7II 4 Fal 0J JUNCTION NUMBERS

S2

3 84 

3 3N

0

PUMP

El

FI3.3. INTACT LOOP, NODALISAT.ION
E] COMPONENT NUMBERS

0 JUNCTION NUMBERS

REFLOOD ASSIST STEAM

BYPASS VALVE GENERATOR

3 SIMULATOR 7 10

\ % BROKEN LOOP / 2

2\\HOT LEG 3 BREAK

22 BREi

PLA

PUMP 2

SIMULATOR ig

AKtNE

BL-1

0 BREAK

t

BREAK

PLANE

FI6.4. BROKEN LOOP NODALIZATION
, 

ON

bp,

BREAK0 6 i S

STEAM

I. I I

I 4 I 3 1 2

C T I I

CONTROL VALVE 23]

I.

I

I 1

2

/

w

® i

2

'.0

00

INTERNAL

COMPONENT NUMBERS

COMPONENT NUMBERS

JUNCTION NUMBERS

FIL

Q-LIZ

n2I

TEE 22 3

-I

TEE nlI

@I © I

STEAM

GENERATOR f'J I

SECONDARY

2Ol, I

I.

~~~~~1

33

2

i

4

-- [

Q •

-- I - - FIG.5. STEAM GENERATOR SECONDARY NODALIZATION
CORE BYPASS COMPONENTS

The top of level 3, third radial ring, is linked for each of

the four azimuthal sectors to the bottom of level 11 (rings 2

and 3) by four TEE components. The horizontal side arms of

the TEEs are connected to the outer surface (ring 3) of level

8.

The arrangement is such that Bypass TEE Components 101 and

103 are connected to r = 3, 8 = 1 (3) at levels 3 and 11,

while Bypass TEE Components 102 and 104 are connected to

r = 3, 8 = 2 (4) at level 3 and r = 2, 8 = 2, (4) at

level 11. (This is to allow for the Upper Plenum Hot Leg

connections in radial ring 3 azimuthal sectors 2, 4 at

level 11).

AEEW - M 2464 40
11

A

COMPONENT NUMBER 50

I

O~h

-HOT COLD LEG

CONNECTIONS

BROKEN LOOP

HOT 

o

LEG \ I

BROKEN LOOP

COLD

LEft

00,

CORE

DOWNCOMER

-CORE BYPAS.aS I-.

INTACTLOOP

COLD

LEG

INTACT LOOP

HOT LEG (

O JUNCTION NUMBERS

1 0.1O50-3291 WIDTH ( m I

VESSEL 0.231 0.1,7 RADIAL NODES

CENTRE

FIG. 61 REACTOR VESSEL NODALISATION
N)

0~

Figure 6.11 Reactor Vessel Tnstrument Locations
!

TIýE FOLLOVING ARE PLOTTED AGAINST REACTOR TIME

PRESSURE ,PE-BL-001

1WInfrirh

2:-

4q

X•

KEY

BOL syM NAME UN ITS

- PRESSURE H/H&*2

LOC, 41/ 0/ 3 ItfEM--PlRES h=I

- PRESSURE , N/1t*q2

LOC= 41/ 0/ 3 flIMEf=PRES INF=2

--.- PE-BL-O01 ,IPA

LOC- 113/ O/ 0 Mfl•rI.PRES INF-3

0. 16E 08

0. 14E 08

0. 12E 08

0. IOE 08

'0. SOE 07

z

0. 60E 0?

0. 40E 07

0. 20E 07

O. ODE O00

0 20 40 60 80 100

REACTOR TI[E , SECONDS

FIGURE 7 INF I JON'S 5 INF 2 ORIG, INF 3 EXP

BROKEN LOOP COLD LEG - EXPERIMENTAL LOCATION BL-1
t%) AA
THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIHE

IMASS FLOw RATE ,FR-OL-105

1Winfrith

Li

K(EY

YM NAME UNITS

I-MSS FLWI RATE *KG/5EC

LOC= All 0/ 3 MNEM--FLOh IW~I

- "ASS FLOV' RATE *KG/SEC

LCC= 41A 0/ 3 ttE1-FLOV IIW=2

---FR-BL.-105 ,KG/SEC

LOC. 32/ 0/ 0 HNEH-FLOV IW-3

X_

C..) ILl

U')

.F0 20 40 60 8011G 100

REACTOR TItlE , SECONDS

FIGURE 9 IHF I JONOSs [HF 2 ORIG, [HF 3.EXP

BROKEN LOOP COLD LEG - EXPERIMENTAL LOCATION BL-I
' i -

THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIME

LIOU1D TEMPERATURE ,TE-BL-OOlA

lWinfritlh

X:'

a%~

KEY

SYm

BOL NAME UNITS

- LIOU1D TEMP'ERATUR~E DOEG.K

LOC= 41/ 0/ 3 hNEII=TEIIL FIlf=

- LIOUIO TEMPERATURIE *OEG.K

LOC= 41/ 0/ 3 IINEII=TEIIL [W=2

--- E-BL-0OIA I0EG.KZ

LOC- 171/ 0/ 0 rINEII-TlCL IW-3

1!

C3

.REACTOR TIME SECONDS I

FIGURE 10 INF I JON'S, IMF 2 ORIG, INF 3 EXP

BROKEN LOOP COLD LEG - EXPERIMENTAL LOCATION DL-I
I

THE FOLLOYING ARE PLOTTED AGAINST REACTOR TItlE

VAPOR TEMPERATURE • TE-OL-OOIC

1Winfrithh

t4I

KEY

SYtI NAIE UN I TS 80L

- VAPOR TEMP~ERATUJRE COE&KI

LOC= 41/ 0/ 3 Il~fH.TEllV IIFat

- VAPOR TEMP'ERATURE D(EG.K

LOCu 41/ 0/ 3 IINEH2IEflV INFF2

---TE-BL-0OIC O K

LOC. 173/ 0/ 0 IINEt1.TICL IW-3

Il

d

tuj

REACTOR TitlE , SECONDS

FIGURE I I INF I'JON'S, INF 2 ORIGg [NF 3 EXP

BROKEN LOOP COLD LEG - EXPERIMENTAL LOCATION BL-t
12*. I

THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIME

PRESSURE ,PE-BL-004

Win frich

cnP.

KEY

5TY NAtME UNITS BOL.

- PRESSURE N/tt1..2

LOC= 41/ D/ 4 h1NE--PREE IWF=O

- PRESSURE .N/"f**2

LOC= 41/ 0/ 4 MINEI--PRES I[F-2

---- PE-BL-004 tIPA

LOC, 1id1 0/ 0 tMEM-PRES INf=3

t

U

0. ldE

0. 14E

0. 12E

0. ICE

0. 80E

0. 60E

0. 40E

O. 20E

0. OOE

16

14

12

10

8

6

4

2

0

0 20 40 60 80 100

REACTOR TIMlE , SECONDS

FIGURE 12 INF I JON'S, INF 2 ORIG, INF 3 EXP

BROKEN LOOP COLD LEG - EXPERI9ENTAL LOCATION BL-4
Sn * .- - & . a

I

THE FOLLOVING ARE PLOTTED AGAINST REACTORT'I.ME

5SURE ,PE-BL-008

lWinfri th

PRES

M'

K~EY

syl NAMIE UNITS

-;- PRESSURE *N/tfo*2

LOC= a AI/ 0/ 5 tWMlI4RE3 rIvW - PRESSURE- ,N/fl*w2

LOCu 41/ 0/ 5 IIN"tW'RES [IkF2

... PE-BlL-008 mphA

10Cc 118/ 0/ 0 IINEII-PRES flW.3

0. 16E 08

0. 14E 08

0. 12E 08

O. IOE 08

16

14

10

0. 80E 07

0.60E 07

0.40E 07

0. 20E 07

0.OOE 00

0t

6

4

2

0

\

t

0 20 40 60 1 80 100

REACTOR TIME , SECONDS

FIGURE 13 INF I JON'S, INF 2 ORIG, INF 3 EXP

BROKEN LOOP COLD LEG - EXPERIMENTAL LOCATION OL-8
.7.~ '-4-,-

THE FOLLOUING ARE PLOTTED AGAINST REACTOR TIME

PRESSURE ,PE-BL-002

IWinfrith

tTj

0~

KEY

SYM NAIE UNITS BOL

- PRESSURE *N/1##2

LOC= 31/ 0/ 3 HNEMIPRES [IWf

- PRESSURE N/M*92

LOC= 31/ 0/ 3 MINE=PRES INF=2

... PE-OL-002 A

Inc. 114/ 0/ 0 IINEII.PRES IWf.3

0. 16E

0. 14E

0. 12E

0. IOE

0. 80E

z

0. 60E

0. 40E

Lu

0

16

14

12

10

8

6

4

2

0

-c

n. 1:

0. 20E

0. OOE

0 20 40 60 80 tOo

REACTOR TItlE ., SECONDS

INF I JON S, INF 2 ORIG, INF 3 EXP

BROKEN LOOP HOT LEG - EXPERIMENTAL LOCATION BL-2

FIGURE 14
THE FOLLOVING ARE PLOTTED AGAIINST REACTOR TIMlE

MIXTURE DENSITY - DE-OL-002A

ti

"3

O's

J~.

U'

I-.

KEY

5Yt BOL NAMIE UNITS

1.0

- MIXTURE DENSITY *KG/1**3

LOC= 31/ 0/ 3 IINE1_=DENM [h=!

- MIXTURE DENSITY ,KG/1*.3

LOC= 31/ 0/ 3 1WEM=DENI INF=2

O. 0

... DE-BL-002A *Will..-3

LOC- 9/ 0/ 0 MNEH.DENM IWI-3

0.6

K)

*

2:

K)

I

2:

N

(3

2:

0.4

0.2

0. 0

0 20 40 60 • . 0 100

REACTIJR TIIIE , SECONDS

FIGURE 15 [MrF I JON'S, INF 2 ORIGe IMF 3 EXP

BROKEN• LOOP HOT LEG - EXPERIMENTAL LOCATION BL-2
}

TIE FOLLOVING ARE PLOTTEO AGAINST

MlASS FLOW RATE ,FR-BL-205

REACTOR TitHE tWinfr'ithI

KEY

SYl NAME UN ITS BOL

-r- MIASS FLOV RATE *KG/5EC

LOC. 31/ 0/ 3 MINEt=FLO/ INFuI 0'•

- I"ASS FLOW RATE *KGISEC

LOC= 31/ 0/ 3 ItiEIH=FLOV IW=2

.... FR-BL-205 ,KG/SEC

LOC- 33/ 0/ 0 WIN•n-FLOV [WF-3

U1 L)

C,)

0 20 40 60 80 o00

REACTOR TIME , SECONDS

FIGURE 16 INF I JONS5, INF 2 ORIG, INF 3 EXP

BROKEN LOOP HOT LEG - EXPERIMENTAL LOCATION BL-2
-o,

THE FOLLOIIING ARE PLOTTED AGATNST REACTOR TIHE

LIOUID TEMPERATURE ,TE-BL-002B

uWinfr|-ih

tr,

M'

K~EY

S NAME hUNTS

-LHIJID rEts'ERATME *DE&.K

LOC: 31/ 0/ 3 IINEII=TE?1L IiI'al

- LIOUID TEMPERATUR~E D0EG.KZ

LOC. 31/ 0/ 3 MNEII:TEI¶L hINF2

---rE-BL-0028 a0EG.KI

LOC- 174/ 0/ 0 I1NWf-ThICL Iif.3

Lii

hIi

0

REACTOR TiME , SECONDS

FIGURE 17 INF I JON'S# INF 2 ORIG, INF 3 EXP

BROKEN LOOP HOT LEG - EXPERIMENTAL LOCATION BL-2
1.*

THE FOLLOVIING ARE PLOTTED AGAINST REACTOR TIME

VAPOR TEMPERATURE . TE-BL-00283 TE-BL-002C

WIn nfr'ith

ti, .I

KEY

SY" NAME UNITS BOL"

- VAPOR TE'MPERATUR E *OEG. K

LOC= 31/ 0/ 3 HtNtE=TEflV IWf=I

- VAPOR TEMPERATURE DOEG. K

LOC= 31/ 0/ 3 flNEtI=TEllV INF=2

---TE-I3L-0028 O EG. K

LOC. 174/ 0/ 0 IINEJI-ThL INF-3

- - TE-BDL-002C OMEG K

LOCz 175/ 0/ 0 liNEt1=ThL INF=3

U'

C3

"REACTOR TIME , SECONDS

FIGURE 18 INF I JON*S, INF 2 ORIG, INF 3 EXP

BROKEN LOOP HOT LEG - EXPERIMENTAL LOCATION BL-2

4
• ":":4") . .. . .. :....

THE FOLLODING ARE PLOTTED AGAINST REACTOR TIIIE

PRESSURE ,PE-BL-003

IWinftqI h

:01

KEY

5Yi NAME UNITS BOL

- PRESSURE *Nf/Il*.2

LOC= 31/ 0/ 17 WfEi=PRES INF=I

- PRESSURE HN/Ho*-2

LOC= 31/ 0/ 17 INEtI--PRES INF=2

.... PE-BL-003 ,tPA

LOC- 115/ 0/ 0 I1NEH-PRES INF-3

LUUI0. 16E- 08

0. 14E 08

0. 12E. 08

0. 1 DE 08

0.80E 07

z

0. 60E 07

0. 40E 07

0. 20E 07

O.00OE 00 It= •I

0 20 40 60 80 100

REACTOR TIME , SECONDS

FIGURE 19 INF I JON'Ss INF 2 ORIG, INF 3 EXP

BROKEN LOOP HOT LEG - EXPERIMENTAL LOCATION BL-3

16

14

12

I0

6

2

0

0L
THE FOLLOUING ARE PLOTTED AGAINST REACTOR TIME Wlin frith

MIXTURE DENSITY ,DE-PC-OOIA

1:11

Ni

4

a,'

4

KEY

SYII NAMiE UNITS

- MIIXTURE DENSITY KIG/?1#*3

LOCa 7/ 0/ 4 1¶Nfl=DENN Ilf=I

1.0

0.8

0.6

- MI!XTURE DENSITY K~G/tf#*3

LOC.= 71 0/ 4 IINEtIOENt IW-12

--- DE-PC-0DIA MIG/"99.3

LOC- 13/ 0/ 0 I1NEII-DENtl INF-3

*4)II

!I

tN

Uz

Nt)I.

i.

6-n 01 N•

0.4

0.2

0.0

REACTOR TIME , SECONDS

FIGURE 20 INF I JON'St INF 2 ORIG, INF 3 EXP

INTACT LOOP COLD LEG - EXPERIMENTAL LOCATION PC-I
A

TIE FOLLOUING ARE PLOTTED AGAINST REACTOR TIME Wlinfrith

MASS FLOV RATE ,FR-PC-100

KEY

SYi BOL NAME UNITS

M-ASS FLOV RATE ,KG/SEC

LOCs 7/ 0/ 4 INEHI=FLOV INF=I

- IIASS FLOI RATE .KG/SEC

LObC 71 0/ 4 HNEIIFLOV INF=2

---- FR-PC-100 ,KG/SEC

LOC. 34/ 0/ 0 IINEIiFLOV INf.3

ui

(In Ln Ni -4

0 20 60 80 I00

REACTOR TitlE , SECONDS

FIGURE 21 INF I JON'S, INF

INTACT LOOP COLD

2 ORIG, INF 3 EXP

LEG - EXPERIMENTAL LOCATION PC-I
THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIME

LIGUID VELOCITY ,FE-PC-OOIA

WWInfritch

ti'

KEY

5Th NAME UN~ITS

- LIrwiD VELOCITY "/SEC

LOCz 71 0/ 1, INEtt=VLt0 tIW~

- LIOUID VELOCITY ,H/SEC

LOC, 71 0/ 4 HNEH=VLIO ItF=2

---FE-.PC-0OIA .11/Ec

LOC. 201 0/ 0 MltltFnE If-3

0 20 40 60 80 100

REACTOR TIME , SECONDS

FIGURE 22 INF 1 JON-S, TNF 2 ORIG, INF 3 EXP

INTACT LOOP COLD LEG - EXPERIMENTAL LOCATION PC-i
THE FOLLOVING ARE PLOTTED AGAINST REACTOR riKE

LIUID TEMPERATURE ,TE-PC-OOlA

1WinfrI thl

:ri

t~)

0~

KEY

90L NAE UN4ITS

- LIOVJID TEtVERARRNE DIEG.K

LOCu 7/ 0/ 4 HNENtTEl1L [F=1

-LIGIJID TEWlERATMJE 0EtG.K

LOC= 7/ 0/ 4 IINffETEIL INF=2

---TE-PC-OOlA *UEG.K

LOC. 161/ 0/ 0 ti~ti-tINCI INF-3

-Ln

%D0

0 20 40 60 80 100

REACTOR TIME ," SECONDS

FIGURE 23 INF I JON'Sl INF 2 ORIG, INF 3 EXP

INTACT LOOP COLD LEG - EXPERIMENTAL LOCATION PC-I
TIlE FOLLOVING ARE PLOTTED AGAINST REACTOR TIMlE

VAPOR TEMPERATURE ,TE-PC-OOIC

W:'

X)

BOL NAME UNITS

- VAPOR TEt1'ERATRJPE ,OEG.K

LOC= 7/ 0/ A KNEH=TEVY IF=l

- VAPOR TEhPERATU:E *OEG.K

LOC= 71 0/ 4HJEI=TEI Y INF=2

--- TE-PC-001C , DEG. K

LOC- 178/ 0/ 0 IINEHI.ttCL- INF-3

ad

0

0 20 40 60 80 100

REACTOR TIME , SECONDS

FIGURE 24 INF I JONS, INF 2 ORIG, INF 3 EXP

INTACT LOOP COLD LEG - EXPERIMENTAL LOCATION PC-I
4) .~- 

* . 0) ".. -:* . --.. +I

THE FOLLOVIUG ARE PLOTTED AGAINST REACTOR TIME

PUtiP SPEED ,FUHCTION

IWintrit',I h

~0

ti,

z

t~j

o~I

KEY

BOL SYl NAE UNITS

:-- P' SPEED *RAD/SEC

LOC= 4V 0/ I 11 EN=SPE0 IHF=t

- PUMP' SPEED , RAD/SEC

LOCc 4/ 0/ 1 tMH=flSPED 1INF2

---FUNCTION

- -RWT ION

u

cn l00 100

200

180

160

140

120

100

80

60

40

20

0

O'

t.-

0 J0 20 o 60 80 10100

REACTOR TIME , SECONDS

FIGURE 25 INF I JON'So INF 2 ORIG, [HF 3 EXP

PUMIP SPEED
i

I

THE FOLLOVING ARE PLOTTED AGAINST

,DE-PC-002A

REACTOR TIME

MIXTURE DENSITY ,fE-PC-O02C

:r,

M'

0.7

NAM1E UIITS

M.IIXTURE DENSITY..- *KG/Il..3

LOC= 1/ 0/ 2 IINEtI:DENMt Ir.,

0.6

- MIIXTURE DENSITY KG/tlo*3

LOCr 1/ 0/ 2 HNEI1.OEN1 IWF22

... DE-PC-002A MtG/flo*3

LOC. 161 0/ 0 INELf.ENtt Ilf-3

0.5

- - DE-PC-002C MGM*11 3/¶

LOCr. 17/ 0/ 0 MNE=DEll tW= E3

0.4

x:(3.

to

U

I

2:

(3

0.32:

0.2

0.1

0.0

0 20 40 60 80 100

REACTOR TlIME , SECONDS

FIGURE 26 INF I JON'So INF 2 ORIG, INF 3 EXP

INTACT LOOP HOT LEG - EXPERIMENTAL LOCATION PC-2
THE FOLLOUING ARE PLOTTED AGAINST REACTOR TIME

IIASS FLOl RATE . FR-PC-201 ,FR-.PC-205

l11infr ith

A

A

KEY

SYM "MJE hUNTS BOL

- MASS FLOV RATE KGC/SEC

L0Cz I/ 0/ 2 MN=fJFLOV ltW.I

- IIASS FLOV. RATE DKG/SEC

LOCs I/ Of 2 I1NEH--FLOV hF.2

---FR-PC-201 ,IG/SEC

LOC. 37/ Of 0 tINEfl-fLOV INF.3

- - VR-pc-2OS ,KG/SEC

LOC= 38/ 0/ 0 MCU1FLOV ItF=3

m'

0 20 40

REACTOR TIME

60 "80

, SECONDS

too

FIGURE 27 INF I JON'S# INF 2 ORIG, [NF 3 EXP

INTACT LOOP HOT LEG - EXPERIMENTAL LOCATION PC-2
STHE FOLLOVING ARE PLOTTED AGAINST REACTOR TIME

LIOUID TEMiPERATURE ,TE-PC-002A

1Winfri h

N

NJ

0~

.5:-

KEY

B NAME hUNTS

-LIOUID rEtvERATUiRE DF-G.K

LOCs 1/ 0/ 2 IINE"=TE"L h~al

-110010 TEMP~ERATURE D1EG.K~

LOC= 1/ 0/ 2 MNEII=TEML INF=2

---TE-PC-002A *0EG.K

LOC- 179/ 0/ 0 fWNH-TiCL [W-3

uil3

REACTOR TIME , SECONDS

FIGURE 28 INF I JON'Sl INF 2 ORIG, INF 3 EXP

INTACT LOOP HOT LEG - EXPERIMENTAL LOCATION PC-2
~TJ

N)

0~

THE FOLLOVIIG ARE PLOTTED AGAINST REACTOR TIHE Win frith

VAPOR TEMIPERATURE ",TE-PC-002A

TE-PC-002C

,TE-PC-002D

KEY

SYII NAME UNITS BOL

-VAPOR TEMPERATURE , DG.

LOC= 1/ 0/ 2 IINEIITEHV IlF1

- VAPOR TEMP~ERArTURE OUEQ K

LOCa 1/ 0/ 2 IINE~zTEHV t=22

--- E-PC-002A D EG.K1

LOC- 1791 0/ 0 tM-IITMlCL [W-.3

- - TE-PC-0028 DEIG.KI

LOC= ISO/ 0/ 0 1INEJI4IICL INFx3

- TE-PC-002C D EG.KI

LOC. 181/ 0/ 0 t1lEMlThlCL IF=3

ON

Ln tx.I C3

0 N0 Io 20 40 100

REACTOR TIHE , SECONDS

FIGURE 29 INP I JON'So INF 2 ORIG, [NP 3 EXP

INTACT LOOP HOT LEG - EXPERIMENTAL LOCATION PC-2
TlE FOLLOWING ARE PLOTTED AGAINST REACTOR TIME

PRESSURE ,PE-PC-002

WInfr ih

a'

KEY

SYM BOL NAME UNITS

- PRESSURE N/to*2

LOC= 1/ 0/ 2 MNEM=PRES INF+I

- PRESSURE * NMo*2

L0Cm 1/ 0/ 2 IHNEM=PRES INF=2

---PE-PC-002 MPIA

LOC. 120/ 0/ 0 flNfl.PRES IW-3

0N

CT%

N

I

0. 16E 08

0. 14E 08

0. 12E 08

0. 1OE 08

O.80E 07

O.60E 07

0.40E 07

0.20E 07

0.O0E 00

16

14

12

10

a

6

4

2

0

,,,

2,

REACTOR TIME , SECONDS

FIGURE 30 INF I JON-S, INF 2 ORIG, INF 3 EXP

INTACT LOOP HOT LEG - EXPERIMENTAL LOCATION PC-2
IIIE FOLLOI/ING ARE PLOTIED AGAINST REACTOR ilE 1WInfrich]

3:

PRESSURE ,O-P39-05.-1

K~EY

0. 16E 08

BOL syI NAME UNITS

- PRESSURE N/"**2

LOC= 8/ 0/ I MEMtPRES |iF=I

- PRESSURE 1/tl*9.2

LOC= 8 0/ I I1NEIIMPRE5 INF=2

0. 14E

0. 12E

0. IOE

--- PI'-PI39-OS-1 . flPA

LOC- 141I/ 0/ 0 ItHEIt.PRES IiE.3

"0. 80E

z

0. 60E

16

14

12

I0

6

6

4

2

0

0. 40E 07

0. 20E 07

0. OOE 00

REACTOR IWuE , SECONDS

F I GURE 31 INIF I JOH'S, INF 2 ORIGg INF 3 EXP

INTACT LOOP HOT LEG - PRESSURIZER
TIE FOLLOVING ARE PLOTTED AGAINST REACTOR TIHE WJin frl h

VATER LEVEL ,LEPDT-P139-008+0. 216

at

K)ý

KZEY

5Th NAME [NITS

' ATER LEVEL. tiETRES

LOC= B/ 0/1 nNEM=LEVE i[r=i

- VATER LEVEL ,METRES

LOC= 8/ 0/ I HNEliM-LEVE Ih=2

... LEPOT-P139-0080. 216, IErRES

LOC- 50/ 0/ 0 MNEII-LEVE IfF-3

0", ON C') ILl

I--

Ul X:

REACTOR TIME , SECONDS

FIGURE 32 INF I JON-S, INF 2 ORIG, INF 3 EXP

INTACT LOOP HOT LEG - PRESSURIZER
THE FOLLOGING ARE PLOTTED AGAINST REACTOR IIHE

VATER LEVEL RLE-ECC-OIA

WInfrith'h

I KEY

syl S N AME UIJ4TS B0L

0,- VATER LEVEL atETRES

*4LOCs 15/ 0/ 1 IINE11--EVE [WlF~

- VATER LEVEL MEfTRES

iacC IS/ D/ 1 HNEtI-LEVE INF=2

---LE-ECC.OIA tlETRES

LOC- 51/ 0/ 0 IINHtILEYE IHF-3

0'

(n'A]

REACTOR TIME , SECONDS

FIGURE 33 INF I JON'S, INF 2 ORIG, INF 3 EXP

EMERGENCY CORE COOLING SYSTEM
THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIHE.

PRESSURE ,PT-P 120-043

IWin fr it h

at3

4%

KEY

5Th NAMIE LINITS

BOL

-PRESSURE ,/1.

LOC= 15/ V/ I IINE=PRES IMW=I

- PRESSURE 11/11*4.

LOC= IS/ 0/ 1 I1NEM1PRES INF=2

... PT-P120-04.3 , HPA

LOC. 131/ 0/ 0 IINMf-PRES hNF-3

4,Uootxr,

0

II

N

4000000

3500000

3000000

250000a

2000000

1500000

1000000

S.

SS%..%bI. *...

* S

4.5

4.0

3.5

3.0

2.5

2.0

1.5

1.0

0.5

C.

•g IllEll•l

0 20 40 .60 80

REACTOR TitlE , SECONDS

FIGURE 34 INF I JON-S, INF 2 ORIG, INF 3 EXP

EMERGENCY CORE COOLING SYSTEM

I00
THE FOLLOVING ARE PLOTTED AGAINST REACTOR TiME

U PLENUM AVG PRESSR ,PE-1UP-OO1A

1Winfrich

I

,KEY

BOL SYM NAME UNITS

U PLENUM AVG PRESSA ,N/H1**2

LOC= SO/ 0/ 1 tNEII=PRUP INftI

- U PLENUM AVG PRESSR .N/M*-2

LOC= SO0/ O I WlNErI=PRUP INW=2

---- PE-IUP-OOIA rPA

LOC. 128/ 0/ 0 INEI-PRES N=-3

0. 16E 08

0. 14E 08

0. 12E 08

0. IOE 08

N

0. B0E 07

z

0.60E 07

0.40E 07

0.20E 07

0. ODE 00

16

14

12

10

8

6

4

2

0

REACTOR TIME , SECONDS

FIGURE 35 INF I JON'S, INF 2 ORIG,

UPPER PLENUM PRESSURE

INF 3 EXP
THE FOLLOVI14G ARE PLOTTED AGAINST REACTOR TIME

0"

KEY

iDOL ISY NAME UNITS

1-LI0 AXIAL VELOCITY tIl/SEC

LOC= 50/ 3/ I NEflM=VL-Z I1==I

- LI0 AXIAL VELOCITY ,Ml/SEC

LOC= /50 3/ 1 IMNEM=VL-Z IHF=2

---FE-SLP-001 "l/SEC

LOC- 29/ 0/ 0 IlNEMl.4E IWf-3

t'3

u I I a;

0.0 '

-0.5

-1.5

-2.o

0 20 40 60

REACTOR TIME , SECC

FIGURE 36 INF I JON'S, INF 2 ORIG, INF 3 EXP

LOWER PLENUM LIOUID AXIAL VELOCITY

60 100

INDS
* . 1.• ' " " "

THE FOLLOUING ARE PLOTTED AGAINST REACTOR TiMlE

LIO AXIAL VELOCITY ,FE-SUP-O01W

1WinInfrith

0~

KEY

I

SYM BOL NAME UNITS

- LID AXIAL VELOCITY H1/SEC

LOCR 50/ 9/ I hNEM=VL-Z [NF=!

- LIO AXIAL VELOCITY *H/SEC

LOC= SO/ 9/ 1 "NEM=VL-Z INf=2

---FE-5UP-O0l M1/SEC

LOC- 31/ 0/. 0 IlNEtl.FE DU'-3

-4

uJ

X:

0 20 40 60. 80 too

REACTOR TIME , SECONDS

FIGURE 37 INF I JON'S, INF 2 ORIG, [NF 3 EXP

UPPER PLENUM LIOUID .AXIAL VELOCITY
TIlIE FOLLOVING ARE PLOTTED AGAINST REACTOR TIME

LIOUID TEMPERATURE ,TE-IST-0O01

1WIn rIrhý

0~~

-J

KEY

BOL HYt NAME UNITS

-LIOUID TEIPEFlATURE I)EG.K

LOC= SO/ WI/ 13 1HEM=TEflL INF=l

- LIOUID TEMIPERATtURE ,DEG.K

LOC= 50/ Ill/ 13 HNEtI=TEHL [IW=2

...rE-IST-001 ,DEG.K

LOC- 201/ 0/ 0 INEM-THCI INF.3

lii

C3

REACTOR r[E , SECONDS

FIGURE 38 INF I JON'S, INF 2 ORIG, INF 3 EXP

DOUNCOMER LIQUID TEMPERATURE AT 5.0 METRES
* *1~. . ~,i.

THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIlME

LIOUID TEMPERATURE. JTE-IST-002

WJin fr Ith

0n

-4

ul

KEY

YM NAME UNI1TS

E3OL

- LlaUID TEW1ERATLMRE ,OEG.K~

LOC= 50/ 10/ 13 IINEt~TEIIL lDfd

-.- LIQUJID TEMP~ERATURE OCEG.K

LOC= 50/ 10/ 13 IINElI=TEKL INF=2

.... TE-IST-002 OiEG.K

LOC- 202/ 0/ 0 MNEt'l-TMCL INF-3

C3

a 20 40 60 80 too

REACTOR TIME , SECONDS

FIGURE 39 [NF I JON'S, INF 2 BRIG, INF 3 EXP

DOWNCOMER LIQUID TEMPERATURE AT 4.2 METRES
THE FOLLOVING ARE PLOTTEO AGAINST REACTOR TIMtE

LOUIO TEMPERATURE ,TE-IST-005

1Winfr'i th

N

N)

0~

KEY

SY NAMIE UNITS

- LJ0(IO TEMP'ERATURE DfEG.K~

LOCz SO/ 7/ 13 MNEII=TEIIL IIF~d

-1(0010O TEMP~ERATUR~E ODEG.K

LOCz 50/ 7/ 13 ?INEtI:TE1L TNF=2

---TE-IST-005 , DEG. K

LOC. 205/ 0/ 0 I¶NEII-TtCL Itf-3

0'

C3 Li

a

REACTOR TitlE , SECONDS

FIGURE 40 INF I JON'S, INF 2 ORIG, INF 3 EXP

DOUNCOMER LIQUID TEMPERATURE AT 2.4 METRES
• •!i• ̧ .. .. :

THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIME

LIOUID TEIMPERATURE ,TE-IST-0h2

WInt. ithl

~l1

I

KEY

SYi NAMIE UNITS

- IOUID tEMPERATuRE ,DEG.K~

LOC. 50/ 1/ 13 flFEttTEiL INF-t

-LIOUID TEMPERATURE ODEG.K

10C- SO/ 1/ 13 tINEHTElIL INFE2

---TE-IST-012 , DEG. K

LOC. 211/ 0/ 0 IlMf-TMIL t[W-3

-4

-4

(a

REACTOR TIME , SECONDS

FIGURE 41 INF I JONS, INF

DOWNCOMER LIQUID

2 ORIG, INF 3.EXP

TEMPERATURE AT 0. 3 METRES
TIE FOLLOWING ARE PLOTTEO AGAINST REACTOR TINlE

L PLENUI IMOi1/FLUX

[Winfric hi

ob

3000

KEY

SM NAMIE UNITS

- L PLENUMf HOWF/LUIX ,KGItS**

- L PLENUMI I1IOt/FUX *KO/HiS..

- - L. PLENUMI l1IO/FLUX ,,KG/tIS..

-4

0,

tn

*/

*"

REACTOR TIUME , SECONDS

FIGURE 42 LINE 1 JONOS, LINE 2 ORIG, LINE 3 EXP

LOVER PLENUM MOMENTUM FLUX
S. .-

:47~ p.

TIlE FOLLOVING ARE PLOTTED AGAINST REACTOR TIME

CORE INLET MASS fLOY

1WInfrith

111

x

hi

KEY

B01. NAMEYM UNITS

- CORE INLET MAS$ FLOVKG/SEC

LOC= SO/ 0/ I MKEMFLCI I[F=I

- COWE INLET MASS FLOVKG/SEC

LOC- 50/ 0/ I IMWETI=FLCI I[fz2

-J 'Li

U')

N

0 20 40 60 80 100

REACTOR TIME , SECONDS

FIGURE 43 INF I JON'S, INF 2 ORIG

VESSEL GLOBALS
.THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIME

CORE OUTLET IIASSFLOV

W-minfritch

CD

KEY

SYM BOL NAIE UNITS

- CORE OUTLET fiASSFLOVKG/5EC

LOC= 501 0/ I liNEJIJfLCD IlNF

- CORE OUTLET I1ASSFLOVKG/SEC

LOC SO, O/ 1 IINElI--FLCO [IF=2

LUtUJ

0 20 40 60 80 100

REACTOR TIhIE , SECONDS

FIGURE 44 INF I JON-S, INF 2 ORIG

VESSEL GLOBALS i
ON,
THE FOLLOIING ARE PLOTTED AGAINST REACTOR TIME

L PLENtH LIO VOL FRAC

lWinfrithh

t~j

0~

KEY

SYM NAME UNITS

BOL

- L PLENM LI VOL FRAC,

LOC- 50/ 0/ 1 HNEH=LFLP tINF=

- L PLENI LIO VOL FRAC,

LOC, 50/ 0/ 1 INE.I--LFLP NF'=2

REACTOR TIE , SECONDS

FIGURE 46 [OF I JON'S, IMF 2 ORIG

VESSEL GLOBALS.
I:

THE FOLLOVING ARE PLOTTED AGAINJST REACTOR TILE

D'CtIJER LIU VOL FRAC

Win fr i r

tp,

M'

KEY

SY"

SOLt M~E UNIITS

- D-COIER LWQ VOL FRAC,

LOCz SO/ 0/ 1 MNEtlI4JDC UF1,I

- D'COMIER LIU VOL FRAC,

LOCm 50/ 0/ I INEIILFDC IF=2

0 20 40 60 80 100

REACTOR TitIE , SECONOS

FIGURE 47 INF 1 JON*S, INF 2 ORIG

VESSEL GLOBALS
CORE LIOUID MIASS

SYl1

BOL NAIE UNITS

- CORE LIOUID IIAS3 ,rG

LOC= 50/ 0/ 1 4tE1WMLi1CR IF=t

- CORE LIOUI MASS KG

LOC= 50/ 0/ 1 fMNEt=LHCR INF=2

0~

20 40 60 80 1O0

REACTOR TIlE , SECONDS

FIGURE 48 .INF I JON'S, INF 2 ORIG

VESSEL GLOBALS I mJ
I -

THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIMIE

VESSEL LIUJID MASS

[Winfrith

ti

KEY

SY" NAtE UNITS

BOL

- VESSEL LIOUID MASS *KG

LOC. 50/ 0/ I MNEMlIlVS INF-.

- VESSEL LWUIIO "IASS KG

LOC= 50/ 0. I HEWH=.LtVS IF=2

co

u'n

REACTOR TIME

FIGURE 49 INF I JON'S, INF 2 ORIG

VESSEL GLOBALS

60 8a

-" SECONDS
.- ..w.:

.I

TIE FOLLOVING ARE PLOTTED AGAINST REACTOR TIMlE

TOT ROO HEAT FLUX

1Winfith

M..

co

ON

KEY

SY" BOL NAIE UNITS

- TOT ROD NEAT FLUX fVAT'3

LOC= 5S/ 0/ 1 HNEtI=ODrT IWF2I

I- 'OT ROD HEAT FLUX *VATTS

1.0C= SO/ 0/ I Iltf-=ORO IWF=2

O. 60E 08

0. SSE 08

0.55E 08

O. SOE 08

0. 40DE 06

0. 35E 08

0. 30E 08

0. 25E 08

0. 20E 08

0. ISE 08

0. IOE 08

0O. 50E 0?

O.OOE 00

40

REACTOR F IME , SECONDS

FIGURE 50 IliF I JON4S, ItiF 2 ORIG

VESSEL GLODALS
THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIME

TOT SLAB HEAT FLUX

WIn fr'ithi

O~h

KEY

SYll NAME UNITS

BOL

- TOT SLAB IfAT FLUX wVATTS

LOCu 50/ 01 l M En4,St.r ItFs=I

- TOT SLAB HEAT FLUX *VATTS

LOC, 50/ 0/ I MI"EI&cOSLT IHF.2

CO,,,,,,

0. 28E 08

0. 26E 08

0. 24E 08

O. 22E 08

0. 20E 08

0. ISE 08

0. 16E 08

0. I1E 08

0. 12E 08

0. IOE 08

0. BOE 07

0. 60E 07

0. 40E 07

0. 20E 07

0. 0OE 00

-0. 20E 07

0 20 40

REACTOR TIlE

60 80 100

, SECONDS

FIGURE 51 INF 1 JON'S, INF 2 ORIG

VESSEL GLOBALS
THE FOLLOIVING ARE PLOTTED -AGAINST REACTOR TIME

L PLEI,' AVG LIQ TEM

WInfi-ch

at

K~EY

SYlI NJEhT

BOL nEUIS

- L PLENI~fl AVG LID T",EH~G.K

LOCw 50/ 0/ 1 tIH~fTIILP [WlE

- L. PLENRI AVG LIU TEN*[I)M

LOC- SO/ 0/ 1 I1MJ1TIP ttF.2

d

'Ua \

i

REACTOR T5IN E , SECONDS

FIGURE 52 IHF I JON-So INF 2 ORIG

VESSEL GLOB ALS
.3 ft ..

THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIRE

CLAIOING TE•P -FINETE-51105-002

1Winfrith

M

KEY

5Thi NAME UNITS HOL

I-CLAMDING TEWI ..FINE,DMlK

LOCa 50/ 1/ 1 IINEzTHCL Itful

C LAMOING TEMP -FINE,ItG.K

LOCs 50/ 1/ I INE~zttsCL (f.?2

- - TE-SHOS-002 DEG(.K1

LOCo 202/ 0/ 0 wHN.IThCL IIF-3

0,

1~

ci

REACTOR TIM3E SECONDS

FIGURE 53 INF I JON'S, INF 2 ORIGs INF 3 EXP

CENTRAL FUEL BUNDLE CLADDING TEMPERATURES
THE FOLLOING ARE PLOTTED AGAINST REACTOR TIME

CLADDING TEfIP -FIE, ýTE-5G06-OI 1

1WInfridt

at)

K~EY

STh HAIIE UNITS

iBOL

- CaflOING TEIIP -FINE,DE6.K

LOC- SO/ 1/ 5 faTEHTICL [W-sI

- C1ADOING TEMlP -FINE.DE6JK

LOC= 50/ 1/ 5 rflNEJITHCL IWf=2

-- TE-5G06-OII , DEG. K

LOC. 278/ 0/ 0 hNMfl.TICL IFW-3

0

0 20 40 60 80 t00

REACTOR TiHE , SECONDS

FIGURE 54 INF I JON'S, INF 2 ORIG, INF 3 EXP

CENTRAL FUEL BUNDLE CLADDING TEMPERATURES
P -

THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIMIE

CLADDING TEMP -FIWE,TE-5106-021

t'J

o~k

KEY

SYfl NAMIE hUNTS BOL

- CLAWlING TEJIP -FINE. DEG.K

LOC. SO/ V/ 9 I9EIHuTfCL [Wlfu

- aMuINu TEM -FfINE,DEojK

LOC. SO/ V/ 9 IIIENuT1CL INF.2

-- TE-5106-021 DOEG. K

LOC- 2961 0/ 0 I1NE-TliCL INF-3

lWinfrithh

I-.

U

0 20 40 60

REACTOR TItlE

80 100

a.SECONDS

+

FIGURE 55 INF I JON'S. INF 2 ORIG, INF 3 EXP

CENTRAL FUEL BUNDLE CLADDING TEMPERATURES
THE FOLLOIVING ARE PLOTTED AGAINST REACTOR TIME

CLADWING TE'P -FINETE-51HO6-O24

lWinfrith1

t')

KEY

Sym N~tE UNITS

BOL

- CLADMING TEMIP -FINEeDEG.K

LOCz SO/ t/ 1O KNEHltThCL [IF-I

- CLACDDIING TEMIP -FJNEDEa.K

LOC= 50/ I/ 10 I'IE1ITtICL [W-f2

- - TE-51106-024 BEG. K

LOC- 285/ 0/ 0 Wl-1T1CL I[F-3

d

\

i

0 20 40 60 80 o00

REACTOR TI•E , SECONDS

FIGURE 56 [NF I JONOS, INF 2 ORIG, INF 3 EXP CENTRAL FUEL BUNDLE CLADDING TEMPERATURES
THE FOLLOUING ARE PLOTTED AGAINST REACTOR TI'E

CLADDING TEMP -FINE,TE-5104-027

1Winfrichl

1.3

a'

KEY

SM NAJIE UNITS

- CLADII~NG rEWi -FJNEDEGK

LOC. SO/ V/ 12 flNEM-THCL 11f.I

- CLADDING TEIIP ..FINE.DEG.IK

LDCii 501 41/12 IJEmTIICL IW&2

--TE-5104-027 , DEG.

LOC. 293f 0/ 0 fNtM.TtiCL [fW-3

ko.

d

REACTOR TIfE , SECONDS

FIGURE 57 INF I JONS, INF 2 0RIG, INF 3 EXP

CENTRAL FUEL BUNDLE CLADDING .TEMPERATURES
'4

.1;

IHfL FOLLOhING ARE PLOT lED AfiAlIII!T REAC1I)I 1HuE

CLADDING TEMP -FINE,TE-5007-031

ll In ff ith

t,')

KEY

sm NAHE NITiS

- CLADDING TEMIP -F1NE*0EG. K

10Cm SO/ 1/ 13 IINExThCL IzIfu

- .CLADDING TEtIP -FINE.DEG.KI

LOC SO/ I/ 13 WEH.THCL h1=2

- - TE-5007-03I *OEG.IK

LOC. 2711 0/ 0 IIWN-ttTiCL llf-3

d

0 20 . 40 60 80 I00

REACTOR TIME , SECONDS

FIGURE 58 INF I JON-So INF 2 ORIG, INF 3 EXP

CENTRAL FUEL BUNDLE CLADDING TEMPERATURES
4 ::.

THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIlE

CLADDING TEllP -FINETE-5106-039.

lWinfrich

I

'.3

1100

K~EY

Nyi AMI UNITS

- CLADDING TEJI -FINEDEG.tK

LOCC SO/ V15 ISINEuTtTItCL [WeiI

- CLAWDING TMWI -FINE1 DEC. R

LOCu SO/ V/ 1S II1OWNCL hl'z2

-- TE-5106-039 ,DGK

LOC- 297/ 0/ 0 tIND-TflL INF-3

ko d

REACTOR TitlE , SECONDS

FIGURE 59 INF I JON-S, INF 2 ORIG, !NF 3 EXP

CENTRAL FUEL BUNDLE CLADDING TEMPERATURES
• i:,

THE FOLLO1IGIO ARE PLOTTED AGAINST REACTOR TItlE

CLADOING TEMtP -FINETE-5104-43.8

1WinInfrith

X1

1000

K(EY

SY WE A UNITS

-CLAMOING rEMIP -FINE,110J

LOC. SO/ V/ 16 MNEM-P.TCL fly.

- CLAD13ING TEfP .FINE1DMGK

LOCs 50 / V 1 IKHE.TtCL [W=2

- - TE-5t04-',3.8DE.

LOC. 294/ 0/ 0 M"~f.TflCL llW.3

'0

0 20 40 60 80 100

REACTOR TIME , SECONDS

FIGURE 60 INF I JON-S,

CENTRAL FUEL

INF 2 ORIG, INF 3 EXP

BUNDLE CLADDING TEMPERATURES
.4

THE FOLLOWING ARE PLOTTED AGAINST REACTOR TIME

CLADOING TEMP -FINETE-5H05-049

Win frI -ithI

>0 950

KEY

SYM B0L NAME UNITS

- .CLADDING TEIP ,-FINE,(EG.K

LOCv 50/ / 17 1NEH=TfiCL TIFaI

- CLADING TEMIP -FINEDEG.K

LOC= 50/ 1/ 17 Hl'EO=TI¶CL I[F=2

- -TE-SH05-0490EK

LOC- 20'ef 0/ '0 I1NEI-ThCL IIV-3

-4

dt

0 20 40 60 80 100

REACTOR TIME SECONDS

FIGURE 61 INF I JON'S,

CENTRAL FUEL

INF 2 ORIG, INF 3 EXP

BUNDLE CLADDING TEMPERATURES
:~ ..

lilt I-flLLiJUING Aft 11011E IAl)AIAIjI5 PLACI:1 IunIIn

CLADDING TEMiP -FINE,TE-SG06-062

I(IIn fr I: h]

X.

KEY

5Thl NAMIE UNITS

- CLADDING IDI1P -fJNE,rnLIC

LOC*~ 50/ 1/ 20 I¶NEIIzTBCL llful

- CLADDING TERiP -FINEnEG.K

LOC. 50/ I/ 20 tHNEll.TKCL IIF-2

-- TE-5Gd064 DG2

LOC.. 281/ 0/ 0 Mn~t-TI1CLI W.3

t

i

0 20 40 60 80 I00

REACTOR TIME , SECONDS

FIGURE 62 INF I JON-So INF 2 ORIG, INF 3 EXP

CENTRAL FUEL BUNDLE CLADDING TEIiPERATURES
I.

THE FOLLOVING ARE PLOTTED AGAINST REACTOR TtIE"

ROD CENTRE TEIIP-FINETC-SDO7-27 ,TC-5009-27

TC-5010-27

IWin fr -thl

i:~i

K~EY

jSYM NAMIE UNIITS

- ROD CEITRE TEIIP-FINEDEG.K

LOC= 50/ 1/ 12 WtI=TMlRC INF=

-ROD CENTRE TEflP-FINE,OEG.K

LOC= 50/ 1/ 12 M"NIITIRC INF=2

---TC-500?-2 DEG.K

LOC- 168/ 0/ 0 tlNfl-TliRC INF-3

- - rC-5009-2? , DEC. K

LOCs 1691 D/ 0 HlNtt=TtIRC IWFz3

- - rC-501O-2? E.

",.0 LOC= 1701 0/ .0 I#Efl=TIIRC INF=3

,4

%Z

0 20 40 60 80 100

REACTOR TIME , SECONDS

FIGURE 63 !NF I JON'So INF 2 ORIG, INF 3 EXP

CENTRELINE FUEL TEMPERATURE
TIE FOLLOUtIG ARE PLOTTED AGAINST REACTOR TIME

CLADDING TElMP -FINETE-2GI-OI1

IUJInfrlth:

L-l

KEY

:3

0

SYW

8OL NAME UNHITS

- CLADDING rEI1P -FINE,DEG.1

LOc- SO,/ S/ 5 NEII.THCL (ifat

- CLAD[ING TEHP -FINEOEOK

LOC= 50/ 5/ 5 HNEMITBlCL IWf-2

---TE-2G14-0II ,0EG.

LOC- 220/ 0/ 0 ltNEflT11CL IWf.3

0

0 hi

I0

REACTOR TIME , SECONnS

FIGURE 64 INF I JON-S, INF 2 ORIG, INF 3 EXP

FUEL ROD CLADDING TEMPERATURES -. PERIPIIERAL BUNDLES

f
I

IIIE FOLL0O*ING ARE ItOlI Lt AGAINSf RILACIURI~ 11O

CLADDING TEMP -FINE, TE-2H13-021

lWin fr'i th

KEY- .' !

A

SYM

BOL NAME UNITS

- CLADDING TEtIP -FINE,*EG.K

LOC= 501 5/ 9 WNEMtTMCL INF-I

- CLADDING TEMIP -FINEDECGK

LOC= 50/ S/ 9 HNEH=TIICL INF=2

--- rE-2tf 13-021 ., OM

LOC- 223/ 0/ 0 llNfltTIICL Wl-3

I--. 0

ILa 0-

I

REACTOR TIME , SECONDS

FIGURE 65 INF I JON'S, INF 2 ORIG, INF 3 EXP

FUEL ROD CLADDING TEMPERATURES - PERIPHERAL BUNDLES
THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIME

CLADOING TEMI"P -FINETE-2G14-030

lWinfrith

X

tj

KEY

SY" NAME 1UNIS BOL

-aMADDING1EWV -F1NE.(DMK

10Cw SO/ S/ 13 fl1fElu4flCL INF-1

- C:LADDING TEMIP -FINE*0EG.K

LOC. 50/ S/ 13 hNEH.ThCL INF-2

---TE-2014-030 , DEG. K

LOC- 221/ 0/ 0 M"Et-TMIL INF-3

P.- 0

REACTOR TIME , SECONDS

FIGURE 66 INF I JON'S, iNF 2 ORIG, INF 3

FUEL ROD CLADDING TEMPERATURES

EXP

- PERIPHERAL BUNDLES

9
THE FOLLOUING ARE PLOTTED AGKINST REACTOR TIHE

CLADOING TElMP -FINETE-2114-039

tWIn fr ithh

I

950

K~EY

syl NAMIE UNITS

- CLAW ING TEO -F IRE,DEG. K

LOCu 50/ a/ 15 MlEM*TflCL ltfut

- CLAWDING TEJIP -FIREtJEG. K

LOCa SO/ 8/ 1S IIIE~sTlCL INFw2

...TE-2114-.039DM

LOC- 229/ 0/ 0 M"~t-ThCL hIW-3

O

0 .F20 . 40 60 80 t0o

REACTOR TItlE , SECONDS

FIGURE 67 INF I JON-So [NF 2 ORIG, TNF 3 EXP

FUEL ROD CLADDING TEMPERATURES - PERIPHERAL BUNDLES
THE FOLLOUI1G ARE PLOTTED AGAINST REACTOR TItlE

CLADOING TEM'P -FINETE-2H13-049

lJWinfrlth

ti'

0'i

KEY

SYf NAE UNITS BOL

- CLAWOING TETIP -FINEDEG.K

LOC= 50/ S/ 17 HNEH=TCL IF=I

- CLAD ING TEMlP -FINE, iMG. K

LOC= 50/ 5/ 17 t(E=lzThICL INF=2

.... TE-2tH13-0W9 ,DEG.K

LOC- 224/ 0/ 0 I1tEHi.TIICL IWf3..

ad

0

0 20 40 60 80 100

REACTOR TiME , SECONDS

L

FIGURE 68 INF I JON'S, INF 2 ORIG, INF 3 EXP

FUEL ROD CLADDING TEMPERATURES - PERIPHERAL BUNDLES

t.
I,

THE FOLLOVING ARE PLOTTED AGAINST REACTOR TItlE

CLADDING TEtP -FINETE-4GI4-OII

ath

4.I~

KEY

SYM NAE UINITS BOL

CL.AOING 'EIP -FJIN,DfE'.K

LOC= 50/ 6/ 5 ftNEJ=ThCL INF=I

-CLAWIOING TEiP -FINE, DEG.K

LOC- 50/ 6/ 5 1IIfI=TItCL IhF=2

-.-- TE-4GI 4-011 .01- EG. K

LOC- 249/ O/ 0 IfM-ITliCL INF=3

I0

Lu

45 - 600 2 a ' 

FIGUR IN ",9. I ."*S ,-* RIIF X

500 ROD C

450

400 , 0 20 40 60. 80 I 00

REACTOR 1"UiE , SECONDS

FIGURE 69. INF 1 JON'S, INF 2 ORIG, INF 3 EXP

FUEL ROD CLADDING TEI1PERATURES - PERIPHERAL BUNDLES
THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIME

CLADDING TEIIP -FINE9 TE-4G08-021

>1j

lb.

KEY

SYm

BOL NAIE UNITS

-- CLADDING TEIMP -FINE,8 DEG.K

LOC= 50/ 5/ 9 MIEt1.TMCL I[F=I

-2- CLADOING TE!iP -FINE,DEG.KLOC= 50/ 5/ 9 MlNEJI-THICL IIF=2

-3-- CLADDING TEMIP -FINEDEG.K

LOC. 50/ 91 9 MIWJIThCL INF-I

-4- CLADDING TE11P -FINEDEG.K

LOC= 50/ 9/ 9 H.EtI=TICL 11Fu2

--- E-4008-021 , DEG. K

LOC= 24~8/ 0/ 0 I¶NEII=ThCL I~w3 I-O0

d

Iii

0

0 20 40 AD 80 100

REACTOR TIME , SECONDS

FIGURE 70 INF I JON'S, INF 2 ORIG, INF 3 EXP

FUEL ROD CLADDING TEMPERATURES - PERIPHERAL BUNDLES
THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIIE

CLADDING TEMP -FINE,TE-AH1W-028

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I:'1

t%)

0~

K~EY

syl NAME UNITS

-CLAflING EIIP .FINE,DEG.K

LOC-' S0/ 6/ 12 MCI-llTtICL hWut

- CLADOIRG TEMIP -FINE,CEG.K

LOC= S0/ 6/ 12 NNEM-T11CL t~z2

---TE-4H14-028 DIEG.K

LOC- 253/ 0/ 0 tt"411fCL IWf-3

I,.j

m

d3

0 20 40 60. 80 100

REACTOR T[I'E , SECONDS

FIGURE 71 [NF I JON'S, INF 2 ORIG, INF 3 EXP

FUEL ROD CLADDING TEMPERATURES - PERIPHERAL BUNDLES
[ TtlE FOLLOWING ARE PLOTTED AGAINST REACTOR TINE

CLADDING TEMP -FINE,TE-4114-039

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X:'

a%

Z.

K~EY

SYM NM~rE UNITS5

- CLADDING FEII -VINE,DEGJK

LOC= 50/ S/ 15 MWNE1=TtCL IV=I

- CLADDING FEfIP .-FINE,DEG.K

LOCc 50/ 5/ 15 IINEI1=ThCL IW=2

[U TE-4114-039 ,DG

LO-257/ 0/ 0 tiW"t-TflCL IWf-3

CO

C,

"I

0

0 20 40 60 80 100

REACTOR TINE , SECONDS

FIGURE 72 INF I JON'S, INF 2 ORIG, INF 3

FUEL ROD CLADDING TEMPERATURES

EXP

- PERIPHERAL BUNDLES
C j

THE FOILOVING ARE PLOTTED AGAINST REACTOR TIRE

CLADDING TEIW -FINETE-6GI4-O!tI

1Winfrith

t~1

I~J

o~h

KEY

S" NAMIE UNITS

*CLADDINGrTEMP -FINE1DEG.lK

LOC= 50/ S/ 5 HN~tl=TttCL DW-1

- CLADDING TEJIP -FINE,DEG.K

10Cw 50/ 8/ S IINEJITMCL I1F=2

---TE-6G14-01l .,DEG. K

LOC- 329/ 0/ 0 INf.TfltCL ItV-3

o0,

IC0-

REACTOR TIMlE ,- SECONDS

FIGURE 73 INF 1 JON'S, INF 2 ORIG, INF 3 EXP

FUEL ROD CLADDING TEMPERATURES - PERIPHERAL BUNDLES
THE FOLLO, ING ARE PLOTTED AGAINST REACTOR TIME

CLADDING TEMP -FINETE-6GI4-030

I

t~3

0~

KEY

B NAME UNITS

- CLAWOI NG TEMP -F INE, BEG. K

LOCw 50/ S/ 13 IINEtI2ThCL IW=I

lWinfrithl

- CLADDING TEMP -.FINE 9D)EG.K

LOC.m SO/ S/ 13 IINEH-TIICL INF=2

---TE-6C14-030 , DE& K

10Cs 330/ 0/ 0 IINEII-TICL [Ff.3

d IREACTOR TIME , SECONDS

FIGURE 74 INF I JON'S, INF 2 ORIG, INF 3 EXP

FUEL ROD CLADDING TEMPERATURES - PERIPHERAL BUNDLES
4 ~.. -'..-.

I

THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIME

CLADDING TEtlP -FtNETE-6Hl1S-026

WIn nfrith

N

t~)

o~I

K~EY

KY AMIE UNITS

- CLAWOING TEJP -FINEDEG. K

LOC= SO/. 7/ It H"%JITflCL IINFnl

- CLAWDING TEPIP -FINE,0E0AK

LOCs SO/ 7/ It ?1WEt1TlCL 11* =2

... TE-6H15-026 , DEG. K

LOC. 335/ 0/ 0 J#EflTflCL IMW.3

I-'. d

0 20 40 60N 8 s too

REACTOR TIME , SECONDS

FIGURE 75 IHF 1 JON-S, INF 2 BRIG, [HF 3 EXP

FUEL ROD CLADDING TEM1PERATURES - PERIPHERAL BUNDLES
THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIME

CLADDING TEMiP -FINETE-6114-039

ti'

N)

0~

4~.

KEY

SYM NAME UNITS

BOL

CLADDING TEMP -FINE,DEG.KI

LOC, 50/ 7/ 15 IMNEMsTIICL INF-I

- CLADDING TEMP -FINEDEG. K

LOC= 50/ 7/ 15 MNE?1=TtCL IIF=2

---TE-6114-039 ,IEG.K

LOC- 5371 0/ 0 I1NMI-TlCL [W-~3

-.a

t',.

IJJ

a:

REACTOR TIME ,. SECONDS

FIGURE 76 INF I JON'S, INF 2 ORIG, INF 3 EXP

FUEL ROD CLADDIPPI TEMPERATURES - PERIPHERAL BUNDLES
THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIME

CLADDING TEM1P -FINE,TE-6G14-O45

WWInfrithh

N

J~. a'

KEY

YM NAMiE UN4ITS

- CaOOING TEWI 4JlNE4 ItC.K

LOC= 50/ Of 16 MNEflxlCL hFat

- CLAWOING TEMiP .-FJNE, tD. K

LOC= SO/ O/ IS HWH-EI$TCL Ufu2

---TE-.6GI4-O'4S , DEG. K

LOC. 331/ O/ 0 t1?MI1TtCL [Wf-3

LaC3 Iii

0

REACTOR TIME , SECONDS

FIGURE 77 INF I JON-S, [NF 2 ORIG, INF-3 EXP

FUEL ROD CLADDING TEMPERATURES - PERIPHERAL BUNDLES
Wlin frith

X~

KEY

Sm" NM NT DOL IMEhT

- PRESSURE N1/tl**2

L0Co 411 0/ 3 tMNEH4RES 1lf.I

- PRESSURE NM*

10C2 41/ 0/ 3 HNE?14'RES INF=2

...PE-OL-001 ,IPA

LOC. 113/ 0/ 0 IIND-PRES flf.3

(N

U

U

r

z

0. 16E 08

0. 14E 08

0. 12E 08

0. IOE 08

0. 80E 07

0. 60E 0?

0. 40E 07

0. 20E 07

0. OOE 00

16

14

12

10

8

6

2

0

REACTOR TIME * SECONDS

FIGURE 78 INF I ORIG, INF 2 ZEROGAP, INF 3 EXP

BROKEN LOOP COLD LEG - EXPERIMENTAL LOCATION BL-1
TIlE FOLLOVINIG ARE PLOTTED AGAINST REACTOR TIlME [Win fri t h

MI XTURE DENSITY ,DE-BL-OOIA

hi

0~

KEY

SYM NAlIE UNITS BOL

- MIXTURE Dot"srr *aKG/.**3

LOC= 41/ 0/ 3 1NEHM=OENH IflHF

- MIIXTURE DENSITY KG"*

L0Cz 41/ 0/ 3 MNEOIOENMt IW=2

.. E-OL-001 A MIG/",*3

L0C- 71 0/ 0 IINEfl.OENH W-3

X:

"IS

E3

0.8

0.7

0.6

0.5

0.4

T-'

(_3

0.3

0.2

0.1

0.0

a 20 40 60 120

REACTOR TIMlE

0 t00

, SECONDS

FIGURE 79 INF I ORIG, INF 2 ZEROGAP, INF 3 EXP

BROKEN LOOP COLD LEG - EXPERIMIENTAL LOCATION BL-1
THE FOLLOING ARE PLOTTED AGAINST REACTOR TIME

IIA5S FLOV RATE ,FR-BL-IO5

1WInfrithh

t~1

01

KEY

SYM NAMiE UNITS

6OL

MASS FLOil RATE ,KG/SEC

LOC= 41/ 0/ 3 1INEH=FL.V IfWI

- MIASS FLOIJ RATE *KG/SEC

LOCz 41/ 0/ 3 MNEMI=FLaV ItW=2

... FR-OL-105 ., KG/SEC

LOC. 32/ 0/ 0 IINEII-FLOV INF-3

9-.

I-.

0% I

I

U

U)

40 60 00

REACTOR itIME , SECONDS

120

FIGURE 80 UNF I ORIG, INF 2 ZEROGAP, INF.3 EXP

BROKEN LOOP COLn LEG - EXPERIMENTAL LOCATION BL-1
9 . 9*°S, t

THE FOLLOUING ARE PLOTTED AGAINST REACTOR TIME

LIOUID TEMPERATURE ,TE-BL-OOIA

jWin fr Ith

tql

KEY

SYM NAME UNITS BOL

- LIOUID TEWERATLIRE DcEG.K

LOCz 41/ D/ 3 HNEH3TEHI. IF=t

-LIOUJID TEIV'ERATURE ,DEG.KLOCu 41/ 0/ 3 I1NEM-TEflL IWf=2

---TE-OL-0OIA DE&KG.

LOC- 171/ 0/ 0 I¶NEII-71CL INF-3

I-.

I-

-.4

1!

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120

REACTOR TIME , -SECONDS

FIGURE 81 INF I ORIG, INF 2 ZEROGAP, INF.3 EXP

BROKEN LOOP COLD LEG - EXPERIMENTAL LOCATION BL-I
THE FOLLOVING.ARE PLOTTED AGAINST REACTOR TIWlE tWinfri h

VAPOR TEftPERATURE ,TE-BL-OOIC

0v

KEY

SYM N4AME UNI!TS SOL

-VAPOR TE1IPERATURE *OEG. K

10C- 41/ Of 3 I¶WEf=TEttV [W-1

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10C= 41/ 0/ 3 I11El1TEMV INF=2

---TE-81.-O0lC 10EG.K

LOC" 173/ 0/ 0 I11O1TfCL INF.3

co

Id

0

REACTOP TIHE , SECONDS

INF I ORIG, INF 2 ZEROGAP, INF 3 EXP

BROKEN LOOP COLD LEG - EXPERIMENTAL LOCATION BL-I

FIGIURIE 82
. .. .• .L .....

THE FOLLOVING ARE PLOTTED AGAINST REACTOR TitlE

PRESSURE ,PE-BL-004

Win nfrith

K~EY

SY". NAME UNITS

- PRESSURE Wtio*.2

LOC: 41/ 0/ 4 ltEH-PRES tWEM

- PRESSURE ,Nln.*2

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---PE-BL-004 ., P

Loc. 116/ 0/ 0 tIolm-PRES INF.3

0. 16E 08

0. 14E 08

0. 12E 08

0. IOE 08

16

14

12

10

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0.80E 07

z

0.60E 0?

0.40E 07

0.20E 07

0.OOE 00

6

4

2

0

REACTOR TIME , SECONDS

FIGURE 83 INF I ORIGo INF 2 ZEROGAP, INF 3 EXP

BROKEN LOOP COLD LEG - EXPERIMENTAL LOCATION BL-4
THE FOLLOTING ARE PLOTTED AGAINST REACTOR TIlHE WInfrith

PRESSURE ,PE-BL-008

KEY0. 16E 08 16 ~KEY

SYMtt•T BOL NAME UNITS

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LOC= 41/ 0/ 5 tINEt--PRES IFI'1

Oy - PRESSURE ,N/Hf,2

LOC. 41/ 0/ 5 HNE=PRE5I 4 -2 0. 12E 08 12

.... PE-BL-008 ,I'PA

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0. IOE 08 10

0. 80E 07? I

0. 60E 07 6

0. 40E 07 4

0. 20E 07 2

0. OOE 00 - ...... .. 0

0 20 40 60 80 100 120

REACTOR TItME * SECONDS

FIGURE 84. INF 1 OR[G, INF 2 ZEROGAP, INF 3 EXP

BROKEN LOOP COLD LEG - EXPERIMENTAL LOCATION BL-8

4
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3

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0. OOE 00

0 20 40 60 80 100

REACTOR tIlE * SECONDS

FIGURE 85 INF I ORIG, INF 2 ZEROGAP, INF 3 EXP

BROKEN LOOP HOT LEG - EXPERIMENTAL LOCATION BL-2

16

14

12

10

8

6

4

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THE FOLLOIVING ARE PLOTTED AGAINST REACTOR TIMiE

MIXTURE DENSITY BDE-OL-002A

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... DE-BL-002A MGM/Iw3

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REACTOR TIME , SECONDS

FIGURE 86 INF I ORIG, INF 2 ZEROGAP, INF 3 EXP

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LOC= 31/ 0/ 3 I"H=FLOV INF=t

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.... FR-BL-205 , KG/SEC

LOC- 33/ 0/ 0 lEftl-FLOV INF-'

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160

140

120

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80

60

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FIGURE 8? INF I ORIG, INF

BROKEN LOOP HOT

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LEG - EXPERMIENTAL LOCATION BL-2
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THE FOLLOINhtG ARE PLOTTED AGAINST REACTOR TIME

LIQUID TEMPERATURE ,TE-OL-0028

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FIGURE 88. INF I ORIG, INF

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VAPOR TEiIPERATURE ,TE-BL-0028 ,TE-ML-002C

Winfrith

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--- E-L-0028 DG

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120

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FIGUPE 89 INF I ORIG, INF 2 ZEROGAP, INF 3 EXP

BROKEN LOOP HOT LEG - EXPERIMENTAL LOCATION BL-2
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PRESSURE ,PE-OL-003

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.... PE-OL-003 'hPA

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07

07

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16

14

12

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REACTOR TItlE * SECONDS

FIGURE 90 INF I ORIG, INF-2 ZEROGAP, INF 3 EXP

BROKEN LOOP HOT LEG - EXPERIMENTAL LOCATION BL-3
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.... FR-PC-IO0 ,K/SEC

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120

REACTOR TIMlE , SECONDS

FIGURE 92. INF I ORIG,

INTACT LOOP

INF 2 ZEROGAP, INF 3"EXP

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II

THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIME jWin fr I th

LIOUID VELOCITY ,FE-PC-0OIA

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FIGURE 93 •INF I OREG, INF 2 ZEROGAP, INF 3 EXP

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THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIIE

LIOUID TEIMPERATURE ,TE-PC-OOIA

cn

46

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5Th NAMIE UNITS (301

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400-

380

360

340

320

300

FIGURE 94 INF I ORIG, INF 2 ZEROGAPo INF 3 EXP

INTACT LOOP COLD LEG - EXPERIMENTAL LOCATION PC-i
TIE FOLLOVING ARE PLOITED AGAINST REACTOR TIHE

VAPOR .TElIPERATURE ,TE-PC-OOIC

1Winf,' Ii

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- VAPOR lEtWPERArWE D[EG.

LOC= 7/ D/ 4 IINEJIWENY IWf=I

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... TE-PC-001C , 11MLK

LOC. 178/ 0/ 0 tW?-lThCL INF-3

(-.,

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120

REACTOR TiME , SECONDS

FIGURE 95 INF I ORIG, INF 2 ZEROGAP, INF 3 EXP

INTACT LOOP COLD LEG - EXPERIMIENTAL LOCATION PC-I.
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£ - .I~. -

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ARE PLOTTED AGAINST REACTOR TItIE

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416

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200

180

160

140

120

100

80

60

40

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REACTOR TIME , SECONDS

FIGURE 96 INF I ORIGs INF 2 ZEROGAP, [NF 3 EXP

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 ASS

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nIXTURE DENSITY ,DE-PC-002A ,DE-PC-002C

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BL NAMIE UlITS

- MIIXTURE DENSITY KGAI#*.3

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LOCm 1/ 01 2 t1N1EMEM INF%2 I IB

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0.5

0.4

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0.2

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120

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80 100

, SECONDS

FIGURE 97 INF I ORIGS INF 2 ZEROGAP, INF 3 EXP

INTACT LOOP HOT LEG - EXPERIIIENTAL LOCATION PC-2
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THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIHE Win fr ith

BASS FLOV RATE *FR-PC-20I ,FR-PC-205

ai

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- MASS FLOU RATE *KG/SEC

LOC. 1/ 0/ 2 WINEHLOV Mal.

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---FR-PC-201 K~G/SEC

LOC. 37/ 0/ 0 tINEB-FLOV tW-3

- - FR-PC-205 ,KG/SEC

10Cs '38/ 0/ 0 hNE1I-FLOV IW.31

REACTOR TIME , SECONDS

FIGURE 98 INF I ORIGs INF

INTACT LOOP HOT

2 ZEROGAP, INF 3 EXP

LEG - EXPERIMENTAL LOCATION PC-2
THE FOLLOVING ARE PLOTTED AGAINST REACTOR TItlE

LIOUIO TEWIPERATURE ,TE-PC-002A

lWin fr i r

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• SECONDS

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FIGURE 99 [NF 1 ORIG,, INF 2 ZEROGAP,, INF 3 EXP

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K fl :1.

THE FOLLOVING ARETPLOTTED AGAINST REACTOR TIHE IWinfrithl

VAPOR TEM.PERATURE ,TE-PC-002A

TE-PC-002C

,TE-PC-0020

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LOCu.- 1/ 0/ 2 IINfIisTEKV If~ut I.

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-- TE-PC-0028 OE.

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REACTOR TIME , SECONDS

FIGURE 100 INF I ORIG, INF 2 ZEROGAP, INF 3 EXP

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THE FOLLOVIING ARE PLOTTED AGAINST REACTOR TIME

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16

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12

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REACTOR TiHE . SECONDS

INF 1 ORIG, INF 2 ZEROGAPs INF 3 EXPINTACT LOOP HOT'LEG - EXPERIMENTAL LOCATION PC-2FIGURE 101
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FIGURE 103 INF I ORIG, INF 2 ZEROGAP, INF 3 EXP

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FIGURE 104 INF I ORIG, INF 2 ZEROGAP, INF 3 EXP

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100 I
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16

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REACTOR TIMlE

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a 20 40 60 s0 100 120

REACTOR Ti"lE , SECONDS

FIGURE 107 INF I ORIG, [HF 2 ZEROGAP, [HF 3 EXP

LOWER PLENUM LIQUID AXIAL VELOCITY
TlHE FOLLOWING ARE PLOTTED AGAINST REACTOR TIRlE

LIU AXIAL VELOCITY ,FE-5UP-001

KEY

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.... FE-SUP-O01 ,I/SEC

LOC- 31/ 0/ 0 t1NIfE IFW.3

0 20 40 60 80 o00 120

REACTOR TitlE , SECONDS

FIGURE 108 INF I ORIGs INF 2 ZEROGAP, INF 3 EXP

-UPPER PLENUM LIQUID'AXIAL VELOCITY

S
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L[tUID TEMPERATURE ,TE-IST-O01

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LOCz 50/ Ill/ 13 I¶If"=TEML Ilf=2

IOCC 201/ 0/ 0 tINEII-ThCL tWf-3

U'

120

REACTOR TIME , SECONDS

FIGURE 109 INF I ORIG, INF 2 ZEROGAPs INF 3 EXP - IOWNCOMER LIQUID TEMPERATURE AT 5.0 METRES
* I

THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIHE

LIOUID TEIMERATURE •,TE-IST-002

1Winfrithh

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-LIQUID TEMPERATURE DM K.

LOCs SO/ 1D/ 13 fl~fHTEIL If.1l

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LOC= 50/ 10/ 13 IEtt.TEflL INF=2

---. TE-IST-002 ,DEG. K

LOC- 202/ 0/ 0 HNL-TIICL II-3

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FIGURE 110 INF I ORIGg INF 2 ZEROGAPs INF 3 EXP

ODUNCOIIER LIQUID TEMPERATURE AT 4.2 IMETRES

a
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LIOUID TEMPERATURE ",TE-IST-OOS

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LOC,, 50/ 7/ 13 MNEl ,EMIEL INF=t

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---- TE-IST-005 DEMGK

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REACTOR TIME

80 100 120

, SECONDS

FIGURE I 1I IHF 1 ORIG, INF 2 ZEROGAP, INF 3 EXP

DOWNCOMER LIOUID TEMPERATURE AT 2.4 METRES
THE FOLLOUING ARE PLOTTED AGAINST REACTOR TIlE

LIOUID TEI'IPERATURE ,TE-IST-012

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- LIGUID TEMPERATURE O1EG.K

LOCi, 50/ 1/ 13 HNEHxTE11L 11W 2

---TE-IST-012 DIEG.K

LOC. 211/ 0/ 0 l#EM.TflCL 11F-3

Co

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120

REACTOR TIME , SECONDS

FIGURE 112 INF I ORIG, [NF 2"ZEROGAP, INF 3 EXP

•DOWNCOMER LIQUID TEMPERATURE AT 0.3 METRES

, %L
.7-.

THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIME

L PLENUM MWOl/FLUX

. NAME UNITS

L RENU PL Mi/FLuX ,I

L PLENUM HO"/FLUX I

*-L PLENUM mtM/FLUX_ I

KGfltS~q

I-. ('aA2:

0 20 40 60 80 100 120

REACTOR TItME , SECONDS

FIGURE 113 -LINE I 0RIG, LINE 2 ZEROGAP, LINE 3 EXP

LOWER PLENUM MOMENTUM FLUX
THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIHE

CORE INLET 11ASS FLOVi

t')

.p.

.11 NAMIE UNI1TS

- CORE INLET MIASS FL0VKG/SEC

LOCm SO/ D/ I IINEJIFLCI h~ut

- CORE INLET MIASS FLOV,tKG/SEC

LOC. SO/ 0/ 1 flNEJI:FLCI IW-2

0L0~

LJ)

U

0 20 40 60 80 100 120

REACTOR TIME . SECONDS

FIGURE 114 INF I ORIG, INF 2 ZEROGAP

VESSEL GLOBALS
Z .

+, . 6.11

THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIMlE

CORE OUTLET MASSFLOV

Winf'r ith

0~

SM MAKE UNITS

SOL

\

- COWE OUTLET 1JAS9FLOVKG/3EC

LOCu 50/ 0/ I 1INeHLCO [Wet

- CORE OUTLET IIASSFLOVKG/SEC

LOC= 50/ 0/ 1 1t•I=FLCO hF=2

ILl

(I)U

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A

40

REACTOR TIME

120

SECONDS

FIGURE 115 INF I ORIG, INF 2 ZEROGAP

VESSEL GLOBALS
THE FOLLOVIG ARE PLOTTED AGAINST REACTOR lIME

CORE LIOUIO HASS

0~

NAMIE UNITS

- CORE 1101110 HASS ,KG

LOCs SO/ 0/ 1 HHEn4IICR r,~nt - CORE LIGUID HIASS K~G

10C= SO/ 0/ 1 I1NEfl-LfCR 1lf=2

p-'

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REACTOR T[ME , SECONDS

FIGURE 116 •INF I ORIG, INF 2 ZEROGAP

VESSEL GLOBALS
ft V°,

Tire FOLLO 1t0 ARE PLOTTED AGAINIST REACTOR TIi"

L PLEWI Li0 VOL FRAC

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IlM AME UNITS

L PLENT1 i(fVOL'#RAC,

LOCz SO/0/ .l1 lINEII-IFIP INW=1 m - L PLE111i LO VOL FRAC,

LOC= SO/ o/ 1 NOI=LFLP If=u2

120

REACTOR TIME , SECONDS

FIGURE 117 INF I ORIG, INF 2 ZEROGAP

.VESSEL GLOBALS
THE FOLLOVING ARE PLOTTED AGAINST REACTOR TitlE

O'COMER 110 VOL FRAC

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n BCOHER L[O VOL. FRIAC,

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- D'COHER LIG VOL FRACS

LOCa 501 0/ I tIN-ENLFDC I1F,,2

1.0

0.

0.

I.-.

0.7

0.6

0.,5

0.4

0.3

0.2

0.1

120

REACTOR TIME , SECONDS

FIGURE 118 WNF I ORIGo INF 2 ZEROGAP"

VESSEL GLOBALS

4

I

THE FOLLOWING ARE PLOTTED AGAINST REACTOR TINE

VESSEL LIQUIJO MASS

1Winfrith1

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KEY

SYM NAME UNITS

BOL

- VESSEL LIOU1O MASS ,KG

LOC= 50/ O/ I IiNEM=LiVS IW'=-

- VESSEL LIQJID MASS ,KG

LOC= 50/ 0/ I ?tEi1..lBVS I[F=2

I-.

vi

t3

120

REACTOR TIME , SECONDS

FIGURE 120 I[F I ORIG, IMF 2 ZEROGAP

VESSEL GLOBALS
VZEI

KEY

THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIME

TOT ROD HEAT FLUX

Winnfrith

I

a'

.r~.

SYM

BOL - NAME UN4ITS

- tOT ROB HEAT FLUX , VATTS

LOCm SO/ 0/ 1 HNEM1OR0T tfzI

- TOT ROD HEAT FLUX *VATTS

LOCx 50/ 0/ 1 IINEO DROT I" F2

L4

14

0. 60E

0. 55E

0. S5E

0. 45E

0. 40E

0. 35E

0. 30E F - •

0 0. 25E

0. 20E

0. ISE

0. IOE

.0SOE

0. ODE

08

08

08

08

08

08

08

08

08

08

08

0?

00

40

REACTOR TIME

120

, SECONDS

FIGURE 121. INF I ORIG, INF 2 ZEROGAP

VESSEL GLOBALS
THE FOLLOVIHG ARE PLOTTED AGAINST REACTOR TIKE

TOT SLAB HEAT FLUX

I

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BOL

- TOT SLAB IEAT FLUX ,VATTS

LOC- 50/ 0/ I ItEH--OSLT INF-u

- TOT SLAB HEAT FLUX ,VATTS

LOC= 50/ 0/ 1 IMNEI=OSLT [hF=2

vi

en

I0. 40E

0. 35E

0. 30E

0. 25E

0. 20E

0. 15E

0. tOE

0. 50E

0. OOE

\,

"l

120

REACTOR TIME

FIGURE 122 INF I ORIG, INF 2 ZEROGAP

VESSEL GLOBALS

, SECONDS

'%

I
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THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIME

L PLENUII AVG LiO TEl

[Winfrith

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5yTh NAMIE LUNTS BDOL

to- L PLENUII AVG LID TE?1,DEG.K

LOCa SO/ 0/ 1 WIM111=T0L Ilfut

- L PLENW AVG L10 TEI1*CEG.K

LOCa SO/ 0/ 1 "NIINl-T)IP 11Fz2

w•v .

540

520 L

So01

4801- --'Ln

-I--- -- - ___ --------- 5 5

Vt

li3

w 4601-

4401-

420 L

4001-

anu

0 20 40 60 80 100 120

REACTOR TIME , SECONDS

FIGURE 123 INF I ORIG, INF 2 ZEROGAP

VESSEL GLOBALS
THE FOLLOUING ARE PLOTTED AGAINST REACTOR TIME

CLADDING TE11P -FINE, TE-5"H05-002

jWinfrithh

X

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KEY

SYtI WAIE UITS

- cAM~ING TEMP -.FINE1IJMKI

LdC- SO/ I/ I flNEJ14HCL hF-t

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LaCs 50/ I/ I tIFFH.ThCL IFF22

-- TE-IO54)02 *DEGK

LOCC 202/ 0/ 0 IINEMII.TCL INF-3

t•. .

0 20 40 60 80 100 120

REACTOR TIME , SECONDS

F I GURE 124 INF I ORIG, [NF 2 ZEROGAP1 INF 3 EXP

CENTRAL FUEL BUNDLE CLADDING TEMPERATURES
THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIME

CLADDING TEMP -FINE,TE-5G06-O1 I

1Winfrithh

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80L NAMIE UNITS

- MMAIJONG TEMP -F INE, OM K

LOCz 5a/ 1/ 5 IiNE?=TMCL IF~im

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10C= 50/ 1I/ 5 HNEII.THMC INF=2

- - TE-5006-0I1 *DEG.K

I CC- 270/ 0/ 0 tMN-lTfMtL tfV-3

0'

0 20 40 60 80 100

a SECONDS

120

REACTOR TIME

FIGURE 125 INF I ORIG, INF 2 ZEROGAP, INF 3 EXP

CENTRAL FUEL BUNDLE CLADDING TEMPERATURES
THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIME

CLADDING TEMP -FINETE-5106-021

WLin f,',it h

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KEY

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DOL NAME. UNITS

- CLAW~ING TEMP -FTH4E,CIEG.K

L0CC SO/ V/ 9 IiNSI.mTKL INFl

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L10C= SO/ V/ 9 li?,VflsTHiCL [IN=2

- - TE-5106-021 , DEG. K

LOC. 296/ 0/ 0 HINWTIICL INF-3

1t

tLii

- .. ,.

0 20 40 60 80. 100 120

REACTOR TIME , SECONDS

FIGURE 126 INF I ORIG, INF 2 ZEROGAP, INF 3 EXP

CENTRAL FUEL BUNDI F CLADDING TEMPERATURES

4
-I..

C TAHE FOLLOVING ARE PLOTTED AGAINST REACTOR TIME

CLADDING TEMP -FINE, TE-5HO6-024

lWinfr t h]

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BOL

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L0C2 50/ 1/ to KN1EfluTttCL (Wut

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10Cm 5O/ If 10 HNEIM27MCL I~fm2

- - TE-5tid06-24 m

LOC- 255! 0/ 0 flH1-TflCL If.3

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900

800

700

67(

500

Lfli

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I I

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20 40 60 80 100 120

REACTOR TitE , SECONDS

INF 1 0RIG, INF 2 ZEROGAP, INF 3 EXP

CENTRAL FUEL BUNDLE CLADDING TEMPERATURES
THE FOLLOWING ARE PLOTTED AGAINST REACTOR TIME

CLADDING TE11P -FINE,TE-5104-027

Otb

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- CLADDING TEMIP -FINEDEG.K

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- - TE-5104-027 , DEM K

IOC. 293/ 0/ 0 IINEHi.TMCL W-N?3

120

REACTOR TIME A SECONDS

FIGURE 128 INF I GRIG, INF 2 ZEROGAP, INF 3.EXP

CENTRAL FUEL BUNDLE CLADDING TEMPERATURES
THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIME

CLADING TEMP -FINE, TE-SDO?-031

1W-In fr It h

1p

0%

KEY

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ILOC= SO/ i / 13 miiH.Tr INFCL

- CLAMDING TEMP -FINE,0CKG

LOCa 50/ 1/ 13 MIBtUTICL hNF=2

- - TE-5D07-031 0M K.

LOC- 2?1/ D/ 0 Il1EI-THlC Wl-3

I-.

120

REACTOR TIME , SECONDS

FIGURE 129 INF I ORIGR INF'2 ZEROGAP, INF 3 EXP.

CENTRAL FUEL BUNDLE CLADDING TEMPERATURES
THE FOLLOVING ARE PLOTTED AGAINST REACTOR TItlE

CLADWING TEMP -FINETE-5106-039

1WInfrich

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-aCLAWING TEMP -V1NEIEG.

LOCu SO/ V/ 15 ZINEII=THCL !NF=t

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-- TE-SI06-039 ,DG

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120

REACTOR TI[lE , SECONDS

FIGURE 130 INF I ORIG, INF 2 ZEROGAP, INF 3 EXP

CENTRAL FUEL BUNDLE CLADDING TEMPERATURES
THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIlE

CLADDING TEI"P -FINETE-5104-43.8

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- CLADDING TEMIP -PINE,CEG.K

LOCa 50/ V1 16 IINEJI.THCL INFI

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LOC: 5O/ V, 16 HNJEH=THCL tWF2

-- 1E-5104-43.8 DOEG.K

LOC. 29'u/ Of 0 tIIMflTICL TNF-3

I,4

80

REACTOR TIME , SECONDS

FIGURE 131 INF I ORIG, INF 2 ZEROGAP, INF 3 EXP

CENTRAL FUEL BUNDLE CLADDING TEMPERATURES
 ̧.9"* ̧

If,

THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIHE

CLADDING TEMP -FRNEJTE-5HOS-0•9

Wuinnfri h

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SYII NAMIE UNITS

-CLADDOING TEMIP ..FJNEOEG.K

LGCz SO/ I/ f7 hM2IITHCL INF-I

900

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LOC- SO, 1/ 17 HWNEIIThL IWf.2

-- TE-5iHOS-04~9 E.

LOC- 284/1 0/ 0 IINFl-THCL It'F-3

I.-

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REACTOR TIME , SECONDS

FIGURE 132 INF I OR[G, INF 2 ZEROGAP, INF 3 EXP

CENTRAL FUEL BUNDLE CLADDING TEMPERATURES
* - -A

THE FOLLOIING ARE PLOTTED AGAINST REACTOR TIME

CLADDING TElMP -FINE,TE-5G06-062

lWin frthl

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SYi BOL NA5E UNITS

- CLABOItG TEIIP -.FINE,DEG.lK

LOC= 50/ 1 / 20 ?HNEHt=TIICL l[11

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LOC= SO/ 1 / 20 IMi=~tTfiCL IW=2

-- TE-S,105-062 MOEG.K

LOC- 281/ 0/ 0 iflEMl-TIICL !NF-3

REACTOR TIMiE , SECONDS

F[GURE 133 INF I ORIG, INF 2 ZEPOGAP, INF 3 EXP

CENTRAL FUEL BUNDLE CLADDING TEMPERATURES
THE FOLLOGING ARE PLOTED AGAINST REACTOR TIIME

ROD CENTRE TEIP-FiNETC-5007-27 ,TC-5009-27

TC-5010-2?

Win fr'Ithi

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KEY

5T tAIEI*T

BO0 NAE UIT

- ROD CENTRE YEhIP-FINE,OEM K

LOC- SO/ 1/ 12 MNM=IThRC IHFat

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LOC. 50/ 1/ 12 ZINE=TlhRC [HF.2

---TC-50017-27 , OEG.

LOC. 1681 0/ 0 IINEtl-TIIRC INF-3

-- TC-5009-27 *DEG.K

LOC. 1691 0/ 0 HNEII.THRC Ilf.3

- - IC-5010-27 E.

LOt. 170/ 0/ 0 ZINEt~TIIRC [W=.3 I-.

-1

0

d

Iil Q

0 20 40 60 80 100 120

REACTOR TIHE , SECONDS

FIGURE 134 INF I CRIG, ENIF 2 ZEROGAPs lWE 3 EXP

CENTREL [NE FUEL TEM1PERATURE

0
THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIMIE 1WInfrith

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080L

I-CLAWDING TEMP ..VINE.I)EG.IK

LOC= S0/ S/ 5 11MHM=TCL hIW=t

I-CLADDING TEMP -FIfE1 DEG.K

LOC= 50/ 5/ 5 MNE1=TMCL INF=2

---TE-2G14-01l ,DEG.'K

ICC- 220/ 0/ 0 1¶NEII-TIICL INF-3

t~j

601 80 SECONDS

120

REACTOR TitlE

FIGURE 135 INF I ORIG INF 2 ZEROGAP# INF 3 EXP

FUEL ROD CLADDING TEMPERATURES - PERIPHERAL BUNDLES
THE FOLLOVIING ARE PLOTTED AGAINST REACTOR TIME

CLADDING TEMP -FINETE-2HI3-021

Win frith-1

KEY

SYM NAME UNITS DOL

- CLADDING TEMP ..IINE,03EG.K

LoC= 5D/ S/ 9 HNEti=TtIC INF~d

- CLADDING TEMP -FINE,DEG.IK

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---TE-21-113-021 *DEG.K

LOC- 223/ 0/ 0 IINfl-711CL Uf-3

,..

Idz

a:

0 20 40 60 80 100 120

REACTOR TUIE , SECONDS

FIGURE 136 INF I ORIG, INF 2 ZEROGAP, INF 3 EXP

FUEL ROD CLADDING TEMPERATURES - PERIPHERAL BUNDLES
4.

... . ..

THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIME

CLADOING TElMP -F[NETE-2G 14-030

lWinfrith

X3

KEY

BOL NAME UNITS

- CLADDING TEMP -FJNE,DEG.K

LOC= SO/ S/ 13 IlNEJ1=TtlCL ItF=1

- CLADDING TEMP -FINEDEG.K

LOC= 50/ 5/ 13 hIINEJ=ThCL WNF-2

I.. E-2GI4-030 , DEG. K

LLOC- 221/ 0/ 0 1nEJ1-THCL Itf.3

I.L

120

REACTOR TIIE SECONDS

FIGURE 137 INF I ORIG, INF 2 ZEROGAP, INF 3 EXP

FUEL ROD CLADDING TEMPERATURES -"PERIPHERAL BUNDLES
THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIME

CLADDING TEMP -FINETE-2114-039

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HOL NM NT

- CLADDING MEIP -FINE,0EG.K

LOC= 5O/ 8/ 15 IINEtfITHCL Wal~

- CLADDING rEMP -FTNE.OEG.K

LOC= SO/ 0/ 15 tllEflTHCL IW=2

---- TE-21l4-039 ,DEG.K

LOC- 229/ 0/ 0 i-NEti-THCL IWF-3

1!

tLi

0

120

REACTOR TIME , SECONDS

FIGURE 138 iNF I ORIGs INF 2

.FUEL ROD CLADDINGZEROGAP, INF

TEMPERATURES

3: EXP

- PERIPHERAL BUNDLES
THE FOLLOIVING ARE PLOTTED AGAINST REACTOR TIME

CLADOING TEMP -FINETE-2H13-049

WJiEnfrith

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SYM

BOL NAME UNITS

- CLADDING TEMIP -FINEDGKJ.

LDC= SO/ 5/ 17 IINE)1=TIICL Nfl=!

- CLADDING TEMIP -FINEDEG.K

LOC= 50/ S/ 17 ltNEi=T1ICL INF=2

... TE-2ti13-049 . DMIC

LOC- 224/ 0/ 0 I1NEti-TMCL IWf.3

U,_

b.i C

120

REACTOR TINE , SECONDS

FIGURE 139 INF I ORIG, INF 2 ZEROGAP, INF 3 EXP

FUEL ROD CLADDING TEMPERATURES - PERIPHERAL BUNDLES
TIE FOLLOVING ARE PLOTTED AGAINST REACTOR TIME

CLADDING TElMP -FINE,TE-4GI4-OII

O~h

KEY

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CLADDING 'EMiP -fINEDEG.K

LOC-= 50/ 6/ 5 iNEIMTMCL INF=t

- CLADDING TElIP -FINE8DEGAK

LOC= SO/ 6/ 5 I1NEl1=TlCL IF=2

...TE-4G14-011 *DEG.K

LOC. 249/ 0/ 0 11NE1I41lCL IWl-3

I.-

14

ON hi

0

a 20 40 60 80 t00 120

REACTOR TIME , SECONDS

FIGURE 140 INF I ORIG, INF 2 ZEROGAP, INF 3 EXP

FUEL ROD CLADDING TEMPERATURES - PERIPHERAL BUNDLES
THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIME

CLADDING TEMP -FINE,TE-4G08-021

1Winfri'I h

x

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-4- CLADDING tEaiP ..FINE,DG.K

LOC= 50/ 5/ 9 tNEM-=TIICL I[FI

-, - CLADDING TEIP -F JNE, DEG. K

LOC= 50/ 5/ 9 HiNEH=TMCL INF=2

-3-- CLADDING TEJIP -FINE,CDEG.K

LOC- 50/ 9/ 9 NEh1-TMCL INF-I

-4- CLADDING TEIP -FINEDEG.K

LOCw 50/ 9/ 9 I#ME=THCL I-f=2

"-..

".,.

---- TE-4GO8-021 ,DEG. K

LOC= 248/ 0/ 0 HNEM=TI1CL hF=3

1ýd2N•

REACTOR TIME , SECONDS

FIGURE 141 INF I ORIG, INF 2 ZEROGAP, INF 3 EXP

FUEL ROD CLADDING TEMPERATURES - PERIPHERAL BUNDLES
* 1⁄4

TiE FOLLOVtNG ARE PLOTTED AGAINST REACTOR TIlME

CLADDING TEIMP -F[NE,TE-4KI4-O2B

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04

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LOC= 50/ 61 12 tffHE=TIHCL [F=aI

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LOC= SO/ 6/ 12 I1NEJ1=TtCL INF=2

---TE-4H1'4-028 *DEG.K

L6C- 253/ 0/ 0 li*O-TflCL INF.3

,-4 0'

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0

120

REACTOR TIME , SECONDS

FIGURE 142 INF I ORIG, INF 2 ZEROGAP, INF 3 EXP

FUEL ROD CLADDING TEMPERATURES - PERIPHERAL BUNDLES
1 ~ I -:

THE FOLLOWING ARE PLOTTED AGAINST REACTOR TIME

CLADDING TEMiP -FINE,TE-4114-039

Wlinlfrith

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SYH NAME UNITS

BOL

- CLADDING TEMIP -FINE,ODMf.K

LOC. 50/ 5/ 15 MNEMzTiCL IW=I

\

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LOC= SO/ 5/ 1S MNEM=TMCL INF-2

...TE-4114~-039 *DEG.K~

LOC- 257/ 0/ 0 l1WN-t1TfCL INF-3

I--.

m

d{

REACTOR TIME , SECONDS

FIGURE 143 INF IORIG, INF 2 ZEROGAP, [NF 3 EXP.

FUEL ROD CLADDING TEMPERATURES - PERIPHERAL BUNDLES
THE FLOVIG ARE PLOTTED AGAINST REACTOR TIME

CLADDING TEIMP -FINETE-6GI4-OI1

1Winfrithl

X

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LOC= 50/ S/ 5 t1NEM41T1CL IWf=I

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LOC= SO/ S/' 5 lINEH=TlhCL Ilf=2

.... TE-63I2/ -0I .DEG.K LOC= 329/ O/ 0 fiNEMI-TIMCL IWF=3

Co 0

C3

REACTOR TIME , SECONDS

FIGURE 144 INF I ORIG, INF 2 ZEROGAP, INF 3 EXP

FUEL ROD CLADDING TEMPERATURES - PERIPHERAL BUNDLES
THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIHE

CLADDING TEIP -FINETE-6GI4-030

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-tCLADDING TEMIP -FINE5DEG.tK

LOCv SO/ B/ 13 llNEIt=7hCL TM'=1

1000

- CLADDING TEMIP -FINE,O)EG.K

LOC= SO/ B/ 13 lINEHTMdICLI[W=2

---TE-6,14.-030 ,DEG.K

10Cm 330/ 0/ 0 IINQ1TIfiCL tNF.3

uJ

d

0 20 40 60 80 100 120

REACTOR TIME , SECONDS

FIGURE 145 INF I ORIG, INF 2

FUEL ROD CLADDING

ZEROGAP, INF 3 EXP

TEMPERATURES - PERIPHERAL BUNDLES
THE FOLLOUING ARE PLOTTED AGAINST REACTOR TIME

CLADDING TEtP -FINE,TE-6HI5-026

1W In fr I-th

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LOC- 335/ 01 0 IINEI1-TICL !NF-3

tola

\

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0 20 40 60

REACTOR TIME

80 100 120

, SECONDS

F!.GUPE 146 INF I DR[Go INF 2 ZEROGAP, IMIF 3 EXP

FUEL RM3~ CLADDlING ThI1PEiRAYURE5 - PERI~PHERAL t~tU"MLES
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THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIME

CLADDING TEMIP -FINEJTE-6114-039

WInfrithl

KEY

5 AYN BOL NAME UNITS

- CLADDING TEIIP -IINEDEG.K

LOCz 50/ 7/ 15 IKNEl1,lCL IhF-I

- CLADDING TEMIP .-FINE,DEG.K

LOC= 50/ 7/ 15 I1NEfl=TML Hf=2

... TE-6114-039 DOE&K

LGC. 3371 0/ 0 flt"I-TfCL IWf-3

1!

IiJ

0

120

REACTOR TIIlE , SECONDS

FIGURE 147 INF I ORIG, INF 2 ZEROGAP, INF 3 EXP

FUEL ROD CLADDING TEMPERATURES - PERIPHERAL BUNDLES
TIE FOLLOVING ARE PLOTTED AGAINST REACTOR TINE

CLADDING TEtP -FINETE-6G14-05

IWinfr'th-1

I:'1

I~J

A

0~

A

550

KEY

SYM NMAE UNJITS VOL

- CLAWDING TEJIP -FJNEDEM K

LOC= 50/ S/ 16 flNEH=ThCL [IEmz

- CLADWING TEJIP -FINEDEG.K

LOC= 50/ 8/ 16 IMNEN=THCL INF=2

... TE-.6Gt4-045 , DEG. k

LOC. 331/ 0/ 0 I¶1Ef-TflCL INF-3

ILl

c'

REACTOR TIME , SECONDS

FIGURE 148. INF I ORIG, INF 2 ZEROGAP, INF 3 EXP

FUEL ROD CLADDING TEMPERATURES - PERIPHERAL BUNDLES
1.

THE FDLLOVING ARE PLOTTED AGAINST REACTOR TIME

PRESSURE ,PE-OL-001

Wi nfr ihl

N)

a'

KEY

SYM

80L NAME UNITS

- PRESSURE ,N/tlo*2

LOC= 41/ 0/ 3 'fNEW=PRES [iF=I

- PRESSURE ,N/M*.*2

L0C= 41/ 0/ 3 MNEMHPRES tNF=2

... PE-OL-001HA

LOC- 113/ 0/ 0 flNEII-PRES hNF-3

I.-

i,

S.

2

0. I6E

0. 14E

0. 12E

0. tOE

O.80E

0. 60E

0. dOE

0. 40E

0. 20E

0. ODE

08

08

08

08

0?

07

07

07

00

16

14

12

10

6

4

2

0

,<

r

0 20 40 60- 80

REACTOR TIME , SECONDS

FIGURE 149 INF I ISHARP, INF 2 ZEROGAP, INF 3 EXP

BROKEN LOOP COLD LEG - EXPERIMENTAL LOCATION BL-t
THE FOLLOVING ARE PLOTTED AGAINST REACTOR TItlE lwinrrithl

MIXTURE DENSITY ,DE-BL-OOIA

tlj

KEY

Syi N4AMIE UNITS

BOL

- MIIXTUJRE DENSITY K~G/M**3

LflC= 41/ 0/ 3 tINEMH4IENI IWf~t

- MIIXTURE DENSITY KIG/M**3

LO3C= 41/ 0/ 3 llNEH=OENII IW=f2

... DE-HL-OO1A MIG/H**.3

LOC. 71 0/ a IitR~EM-Gi INV-3

1.0

0.8

0.6

cm

I.- 1'6

NI t')

If

N-

(_9

0.4

0.2

0.0

0 20 40 60 80 100

REACTOR TIME , SECONDS

F[GURE 150 [NF I [SHARP, TNF 2 ZEROGAP, [NF 3 EXP

BROKEN LOOP COLD IEG - EXPERIMENTAL LOCATION BL-1

J

i
THE FOLLOVING ARE PLOTTED AGAINST REACTOR TitlE Wlinfrith1

HASS FLOV RATE ,FR-BL-105

IN

K~EY

SY AME ItIITS DOL

MASS FLOU RATE *KG/SEC

ILOCm 41/ D/ 3 tlJI1FLOV flVI

- M5AS FLOV RATE ,KG/SEC

LOCa 41/ 0/ 3 IINEHLOV hIN~2

... FR-OL-105 KG/SEC

LOC- 32/ 0/ 0 Wa-114LOV [W?-3

I.-

-4

U'a

-100

0 20 40 60 80 Ica

REACTOR TIME , SECONDS

FICUPE 151 IHF I ISHARPs INF 2 ZEROGAP, [NF 3 EXP

BROKEN LOOP COLD LEG - EXPERIMENTAL LOCATION BL-I
THE FOLLOtING ARE PLOTTED AGAINST REACTOR TINE

LI0UID TEIIPERATURE ,TE-OL-OOIh

[w~~Inf

x

K~EY

Nyi AM UNITS HOL.

- LICAUJI YEWSERATME D1EG.K

LOCz 4.1/ 01 3 HNEJ=TIdVl [Iful

- L10010 TEMP2

ERATUR~E DIEG.K

LOC= 4f/ 0f 3 HNflt3TEHL Irf=2

... TE-BL-OOIA - , EG K

LOC- 171/ 0/ 0 l1Ift1-TflCL IWf-3

0 20 60 80 I00

REACTOR TIME , SECONDS

FIGURE 152 INF I ISHARP, INF 2 ZEROGAP, INF 3 EXP

BROKEN LOOP COLD LEG - EXPERIMENTAL LOCATION BL-I

r
THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIME

VAPOR TE!,PERATU)RE ,TE-BL-O0IC

IWinfrithi

a'

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KEY

)l NAHE t*,! TS

Y-APaR TEMPERATURE *OEG.K~ ILOC. 41/ 0/ 3 hHEII-TEll 1WF.1

- VAPOR TEMP~ERATUJRE DCEG.K

LOCx 41/ 0/ 3 HNifH=TEIIV IW=2

--- E-fL-0OIC 0&

LOC- 1731 0/ 0 ItM.THCL Itf.3

Co

1!

100

REACTOR TIliE , SECONDS

FIGURE. 153 INF I ISHARP, INF 2 ZEROGAP, INF 3 EXP

BROKEN LOOP COLD LEG - EXPERIMENTAL LOCATION BL-1
THE FOLLOWING ARE PLOTTED AGAINST REACTOR TIME

PRESSURE ,PE-BL-004

1Winfrith

t~J

'.3

a.'

KEY

S 14 AME tNITS

- PRESSURE ~ /l.

LOC= 41/ Of 4 tiNEll=PRES h(=I

- PRESSURE *H/H*o2

10Cc 41/ 0/ 4 tWEtl=PRES [W-2

---PE-OL-004 , MPA

LOC- I Id/ 0/ 0 rlNEfl-PRES flf-3

'.0

C

O. 16E 08

0. 14E 08

0. 12E 08

0. 1OE 08

N 0. 80E 07

z

O. 60E 07

0. 40E 07 ?

0. ODE 0?

0 20 .0 60 80

REACTOR TIME , SECONDS

FIGURE 154 INF I ISHARPI INF 2 ZEROGAP, INF 3 EXP

BROKEN LOOP COLD LEG - EXPERIMENTAL LOCATION BL-4

16

14

12

10

a

-'5

6

4

2

0
t. 1%

THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIHE

PRESSURE ,PE-OL-OO0

WInerithh

I~J

O~h

KEY

SY" NAMI UNITS5 BOL

- PRESSURE N1**2It.

LOCs 41/ 0/ 5 HNEH4PRES lF.I

- PRESSURE H/1/,,2

LOC, 41/ 0/ 5 NtEH&PRES (NF-2

...PE-BL-006 MPVA

LGC. I18/ 0/ 0 IlifH-PRES INf.3

I-.

I0. 16E 08

0. 14E 08

.0. 12E 08

0. ICE 08

0. IOE 07

z

O. 60E 0?

). 40E 0?

0. 20E 07

0. DOE 00 ........ .....

o 20 40 60 60

REACTOR TIIE , SECONDS

F[IGURE 155 INF I [SHARP# INF 2 ZEROGAP, INF 3 EXP

BROKEN LOOP COLD LEG - EXPERIMENTAL LOCATION BL-8

16

14

12

10

6

4

2

0

100
THE FOILOVING ARE PLOTTED AGAINST REACTOR tlHE Wllnfrith

PRESSURE ,PE-BL-002

~KEY KEY0. 16E 08 16

t SOLYt NAIE UNITS

N. 0: 14E 08 

14 - PRESSURE HN/fl**2

LOC= 31/ 0/ 3 1HNEM-PRES IMf=I 0'

- PRESSURE Wlh*2

LOC= 31/ 0/ 3 tiNH---PRES IF=2 0. 12E 08 12

.... PE-OL-002 .IVPA

LOC= 114/ 0/ 0 Ittli-PRES IWF-3

0. IOE o0 to

'0. WEO 07 IL.

r

0. 60E 07 6

0. 40E 07

0. 20E 07 2.

0. OOE O0 0

20 40 60 80 100

REACTOR TIE , SECONDS

FIGURE 156 INF I [SHARP$ INF 2 ZEROGAP, INF 3 EXP

BROKEN LOOP HOT LEG - EXPERIMENTAL LOCATION BL-2
1 -, j I 41.f

THE FOLLOUING ARE PLOTTED AGAINST REACTOR TIME 1Winfrit

MIXTURE OWS•ETY ,OE-OL-002A

KEY

syI NlAME" UNITS HOL

- IIXTtYlE OIISITY ,IKG/mloo,

LOC= 31/ 0/ 3 IMNEMB=fERI" hf=I

1.0

0. 8

0. 6

- iIIXTlE i1•NSlTY *KG/M**3

LOC= 31/ 0/ 3 11Efl"3ENH IF=2

.... DE-BL-002A tGmqn.03

LOC- 9/ 0/ 0 II,,fl.DENH tW.3

U

a

2:

U

tNl) IF

"I

2"

0.4

0.2 0.0

a 20 40 60 80 I00

REACTOR TIME , SECONDS

F[GUJRE 157 INF- I [SHARP, [HF 2 ZEROGAPs [HF 3 EXP

BROKEN LOOP HOT LEG - EXPERIMENTAL LOCATION BL-2
THE FOLLOVING.ARE PLOTTED AXGIA4ST REACTOR TitlE lWinfri I

tHASS FLOU RATE ,FR-BL-205

t%)

0~

KEY

BOL~ tS

- MIASS FLOW RATE Mt/SEC

10C* 31/ D1 3 I1NUflFLOV Iulft

- MIASS WNO RATE KG/lSEC

LOCa 31/ 0/ 3 t1NEaFLOV IFV.2

---FR-OL-20S KIG/SEC

LOG. 33/ 0/ 0 WAM-Fl.LOhl (W.~3

Iflu - I

160

140

120

100

I.- C3)

toi

80

60[

40L

j 'a a S

* a.

I.'

h

~ jh 4 ~ S.e* s

20oI

I

0 20 60 80 100

REACTOR TIlE , SECONDS

F I GURE 158 IF ) ISHARP, RIF 2 ZEROGAP, IMF 3 EXP

BROKEN LOOP HOT LEG - EXPERIMENITAL LOCATION BL-2

- r,
THE FOLLOUING ARE PLOTTED AGAINST REACTOR TIIE

LIOUID TEHPERATIJRE *TE-BL-0O2B

lWinfri h

atT

.p.

KEY

SYM

DOL NAMIE UNITS

- LICUID TEMPERATUR~E *DEG.K~

LGCm 31/ 0/ 3 tl*E~lurEfL IWmI

- LIOUJO TE11PERAMIR OlEG.K~

10C= 31/ 0/__3 htEfh=TEIL [FF=2

580

560

540

520

... TE-OL-0028 DG.

'CC* M!~ 0/ 0 IINFII.TMCL IWf.3

U,

a~

540

4,80

460

440

420

400

0 20 40 60 80 100

REACTOR TI[E , SECONDS

FIGURE 159 INF I ISHARP, INF 2 ZEROGAP, INF 3 EXP

BROKEN LOOP HOT LEG - EXPERMIENTAL LOCATION BL-2
TIlE FOLLOING APIE PLOTTED AGAINST REACTOR TIME Iwinfri ~hI

VAPOR TEMPERATUIRE ,TE-BL-0028 ,TE-DL-O02C

N)

01

620

KEY

BOfl NAME UNITS

VAPOR TEI1PERAT.RE DOEG.K

LOCi 31/ 0/ 3 MNEt-TEHV [lHF'

- VAPOR TEWPERATLIE , DEG.K

LOC= 311 0/ 3 MNXEIf=TEIV IWf=2

---- IE-BL-0028 OCEG.K

LOC- 1741/ 0/ 0 flE-fl-THCL [NF-3

--- TE-BL-002C DErG.K

LOC= 175/ 0/ 0 i*tl=TI'CL 1F=3

d

ILi

REACTOR TIME , SECONDS

FIGURE 160 [HF I [SHARP, INF 2 ZEROGAP, INF.3 EXP

BROKEN LOOP HOT LEG - EXPERIMENTAL LOCATION BL-2

-4
:1k

THE FOLLOUUJG ARE PLOTTED AGAINST REACT011 TIMlE Uiinfriti

PRESSURE ,PE-BL-003

N)

A

0~

A

KEY

Sym NAME UNITS

BOL

- PRESSURE ,N/Io,*2

LOC- 31/ 0/ 17 f•lO-PRES IW-I

- PRESSURE N/M*2

LOC. 31/ 0/ 17 IFt-t.PRES IF=2

.... PF_-RL-003 , tPA

LOC- 1151 0/ 0 I/ t -PRES F=-3

0. 16E 08

r

0. 14E

0. 12E

0. IOE

o0. OE

0. 60E

16

14

12

10

B

6

4

2

0

".0

0. 40E

0.20E

0. OE

REACTOR TIMlE , SECONDS

FIGURE 161 INF I ISHARP, INF 2

BROKEN LOOP HOT LEG

ZEROGAP, INF 3 EXP

- EXPERIMENTAL LOCATION BL-3
THE FOLLOWING ARE PLOTTED ArAINST REACTOR TIlME

MIXTURE DENSITY ,DE-PC-OOIA

1WinfErichl

hi

4~.

KEY

SM NAMlE UI~iTS

- DlIXTURE DEWSITT *KG/11**3

LOC= 7/ 0/ 4 ttNEtt-DEMI ItF=I

1.2

1.0

0.8

- nIXTURE DENSITY aKG/Ho*3

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... DE-pc~-00IA *ti/H*93

LOt- 13/ 0/ 0 IINEfI.DENt1 Ilf-3

CO

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m

to

0.6 B

2:

ci

2:

0.4

0.2

0.0

100 0 20 40 60 80

. REACTOR TINE , SECONDS

F I URE 162 IMF 1 I[HAPPo It-I 2 ZEROGAP, !NF 3 EXP

INTACT LOOP COLD LEG - EXPERIHENTAL LOCATION PC-I
THE FOLLOVING ARE PLOTTED AGAINST REACTOR TWfE

HIASS FLOI RATE *FR-PC-100

KEY 350

BOL AMEhlS300,

- ttA33 FLOV RATE *KG/3EC

L0Cz 7/ D/ 4 ?¶NEf11JL0CIf.

M lASS FLOI RATE K~G/SEC

LOC= 71 0/ 14 IINOtILOV IWF=2

Mf-pe-I00 ,KG/SEC 200-

LOC. 34/ 0/ 0 IINHt1.LDV IW-3

ISOS100-

N '

UIl

Ali
THE FOLLOWING ARE PLOTTED AGAINST REACTOR TitlE

LIOUIJ VELOCITY ,FE-PC-OOIA

WInfri' ch

I~3

KEY

S" NAMIE UNITS

BOL

-. ý LIOIJbO VELOCITY ,flSEC

LOC- 7/ 0/ 4 rWNIIVLIQ IFzd

- 111110 VELOCITY WItSEC

LOC= 71 0/ I, IIIEttWLt I~lv2

---FE-PC-001A ,tt/SEC

LOC. 20/ 0/ 0 I1NEJ-FE IW-3

0

0 'Li

uin

REACTOR TItME , SECONDS

FIGURE 164 INF I ISHARP, INF 2 ZEROGAP, [NF 3 EXP

INTACT LOOP COLD LEG - EXPERIMENTAL LOCATION PC-!
THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIWE

LIOUIrD TEIPERATURE ,TE-PC-O01A

1Winnfrich

X

KEY

S" NAMIE UNITS

-LIOUID rEtIPERATURJ ErG..K

LOC* 7/ 0/ 4 m~tMTEIIL hE'*I

- LICUID TEWERA11IRE ,[JEG.K

LOC. 71 0/ 4 hIEllTEI. IW=2

... E-PC-001A E.

LOC- 1761 D/ 0 M"f~-YIICL [W-.3

V

CL

a• 0

0 20 40 60 80 100

REACTOR TitlE , SECONDS

FIGURE 165 INF I ISHARP, INF 2 ZEROGAP, INF 3 EXP

INTACT LOOP COLD LEG - EXPERIMENTAL LOCATION PC-I
T

TE• FOLLOVING ARE PLOTTED AGAINST REACTOR TIRE

VAPOR TEMPERATURE ,TE-PC-OOIC

IWin fr it I

3:

K~EY

SYN NAME UNITS

- VAPO TEMP~ERATRwE 0CEG.K~

LOC= 71 B/ 4 hNEJI4EfIV 1If-t

-VAPOR TEMP~ERATUR~E O[EG.K

LOC= 7/ 0/ 1, HNEtHIEHV NF =2

---TE-PC-001C O~EG.K

LOC. 1781 0/ 0 fiNEII-ThCL ltt.3

0

ICl

0 20 40 60 80 100

REACTOR TIME , SECONDS

FIGURE 166 INF I ISHARP, INF 2 ZEROGAP, INF 3 EXP

INTACT LOOP COLD LEG - EXPERIMENTAL LOCATION PC-i

w U p
THE FOLLOING

PUMP SPEED

ARE PLOTTED AGAINST REACTOR TIME

,FUNCTION

iWin fr ithh

3:

KEY

SY NAMIE UNITS BOL

- PUM SPEED RAO/SEC

LOC= V1 0/ I NEII=SPED INF=I

- Pt" SPEED , RAD/SEC

LOC= V1 0/ I INEDI=SPED tFi=2

-- FUNCT ION

U)

200

180

160

140

120

100

80

60

40

20

0

tN• 0

0 20 4a

REACTOR TIME

60 80

, SECONDS

too

FIGURE 167 INF I ISHARP, INF 2 ZEROGAP, INF 3 EXP

PUMP SPEED
THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIME

MIXTURE DENSITY ,DE-PC-002A *OE-PC-0O2C

1WInfrieh

t~)

A

0~

A

KEY

BOL STM NAME IUITS

- tIXTURE DENSITY *KG/H**3

LOCa I/ O 2 MINEN=DENH hW1=

- MIXTURE DENSITY KM*IGf.3

LOCu I/ Of 2 fiNEII=1ENt1 11Eu2

--- E-PC-002A .1iG/11*93

LOC- 161 0/ 0 IINEti-DENII INF-J1

- - DE-PC-.002C tl~/fi**3

LOC= 171 0/ 0 IINEI=DENHII hE3

0

H)

I

I

2:

0.7

0.6

0.5

0.4

t)

I

I

2::

0.3 2:

0.2

0.1

0.0

0 20 40 60 80 100

REACTOR TIME , SECONDS

FIGURE 168 INF I ISHARP, INF 2 ZEROGAP, INF 3 EXP

INTACT LOOP HOT LEG - EXPERIMENTAL LOCATION PC-2
THE FOLLOiING ARE PLOTTED AGAINST REACTOR TItlE

tHASS FLOV RATE JFR-1C-201 JFR-PC-205

[Winfrith]

I',

A

0'~

A

KEY

sy BOL HAKE UNITS

- MA55 FLO'J RATE *KG'SEC

LOC- I/ D/ 2 tIJFLDV INFI-

- HIASS FLOVI RATE , KG/SECI

LOC= 1/ 0/ 2 IN~izEtFLOY IW.21

... FR-PC-201 K3G/SEC'

WfC- 371 0/ 0 tWEI-FLOV f(W-3

-- FR-PC-205 ,KG/SEC

LOC. 38/ 0/ 0 t#t-~FLOl [W-.3

a) I.L.

0

0 20 40 60 60

REACTOR TItE SECONDS

too

FIGURE 169 INF I ISHARPr INF 2 ZEROGAP, INF 3 EXP

INTACT LOOP HOT LEG - EXPERIMENTAL LOCATION PC-2

i
S.

TiIE FOLLOVING ARE PLOTTED AGAINST REACTOR TIME

LIOUID TEMPtERATURE" TE-PC-002A

WInfrithh

N)

a'

K~EY

S" NAIIE UNITS

-itLIlUD TEtVERAWbRE DEJG.K

LOC= f/ 0/ 2 MNEnrTEtL INF-t

AA

-LIQUID TEMP'ERATURE *OEG.K

Iocz 1/ 0/ 2 HNHIEHf=TfL IW-f2

--- E-PC-002A DIEG.KI

LOC- 1791 0/ 0 I1NEfl.TICL IWI-3

0

0'

v, d'

20 40

REACTOR TIfE , SECONDS

FIGURE 170 INF I [SHARP, INF 2 ZEROGAP, INF 3 EXP

INTACT LOOP HOT LEG - EXPERIMENTAL LOCATION PC-2
4W

TIHE FOLLOWING ARE PLOTTED AGAINST REACTOR TIME lWinfrithl

VAPOR TEMPERAITURE ,TE-PC-002A

TE-PC-002C ,TE-PC-002D

W

4b

Och

K~EY

S NMIE UIT41S

- VAPOR TUtIPERATURE *OEG.K1

LOCn If Of 2 HN~EMlnTEflY f1fzI

- VAPOR TI'ERATURE *VMGK

LOC= If O/ 2 IlEH=TEIIV IWF-2

---TE-PC-002A i , DEG. K~

LOC- 1791 0/ 0 MEHt-TflCL rW-3

- - TE-PC-0028 D EG.K~

LOC= 180/ O/ 0 tfIEfflTfCL flV=3

-- TE-PC-002C . , OEG. K

LOC= [Of/ 0/ 0 NNEKdflCL [WE=3

0,

*-.

too

REACTOR TIM1E , SECONDS

FIGURE 171 INF I ISHARP, INF 2 ZEROGAP, INF 3 EXP

INTACT LOOP HOT LEG - EXPERIMENTAL LOCATION PC-2
THE FOLLOVING ARE PLOTTED AGAINST REACTOR TItlE

PRESSURE ,PE-PC-002

[Winfrithh

til

0

KEY.

SYH NAME UNITS BOL

- PRESSURE N/f14..2

LOC- 1/ 0/ 2 11NEM1PRES flF=l

- PRESSURE NH/H1**2

LOC= 1/ 0/ 2 UINEt1=PRES INF=2

---PE-PC-002 ,11'A

LOCs 1201 0/ 0 flNEtl-PRES IW&3

N

I

N

2

0. 16E

0. 14E

0. 12E

0. IOE

0. 80E

0. 60E

0. 40E

0. 20E

0. OOE

08

08

08

08

07

07

07

0?

00

16

14

12

10

8

6

4

2

0

0 20 40 60 80

REACTOR TIME * SECONDS

FIGURE 1.72 INF I ISHARP, INF 2 ZEROGAP, INF 3 EXP

INTACT LOOP HOT I.EG - EXPERIMENTAL LOCATION PC-2

I&
.. .... . . . .. ~ ~.-.!. . . of

I

THE FOLLO'JING ARE PLOTTED AGAINST REACTOR TIME

PRESSURE ,PT-P139-05-1 I

at'

.V6

KEY

SBtt NAME UNITS

- PRESSURE N.11002

LOC= B/ D/ I IMNEf--PRES INF!

- PRESSURE *N/t"**2

LOC= 8/ 0/ I I?1ME=PRES [WF=2

0. 16E 08 16

Win fr I th]

0. 14E

0. 12E

14

--Pf -P139-05-I P

LOC- 141/ o/ 0 flNEMl.PRES INF-3

0

0. IOE

0. BOE I:

0. 60E

0. 40E

0. 20E

0. OOE

2:

12

10

a

6

4

2

0

FIGURE 173 INF I ISHARPI INF 2 ZEROGAP, INF 3 EXP

INTACT LOOP HOT LEG - PRESSURIZER
THE FOLLOVIHG ARE PLOTTED AGAINST REACTOR TIME 1Wlinfrich

VATER LEVEL ,LEPDT-.P139-0080t. 216

I

t.

KEY

SYtI NAMIE UNIITS B(JL

- V/ATER LEVEL MIErRES

LOC= B/ 0/ 1 MNE11=LEVE IWlf=

- VATER LEVEL flTURES

LOC= B/ 0/ 1 fliEMLEVE IWf:2

---LEPOT-Pt39-.0080. 216,Mif RES

LOC- SO/ 0/ 0 HNEMf-LEVE TIV-3

cn

Lii

I00

REACTOR TIHE ,-SECONDS

FIGURE 174 INF I ISHARP, INF 2 ZEROGAP, INF 3 EXP

INTACT LOOP HOT LEG - PRESSURIZER
-u

THE FOLLOVING ARE PLOTTED AG~AINST REACTOR TIMlE

VATER LEVEL .LE-ECC-.OlA

Wl fnfrt ith

X'

KEY

Syh NAME UNITS

BOL

- WATER LEVEL M liTE"S

LOC= 15/ 0/ 1 HINEI=LEVE IF-=

- WATER LEVEL t lETRES

LOC= IS/ 0/ I HINE--tEVE hF=2

---LE-ECC-OIA *IETRES

LOC- 51/ D/ 0 nNEfl.LEVE hIW-3

(I~

bii

a 20 40 60 so 100

REACTOR TIME , SECONDS

FIGURE 175 INF 1 ISHARP, INF 2 ZEROGAP, INF 3 EXP

EMERGENCY CORE COOLING SYSTEM
THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIME

PRESSURE ,PT-P120-043

Iwinfrithh

A

0~

A

KEY

SYM NAME UNITS

BOL

- PRESSURE HN/H**2

LOC= 15/ 0/ I HINEI=PRES INF=I

- PRESSURE , N/t1..2

LOCC IS/ 0/ 1 11NENMPRES TNF=2

---PT-P120-043 tiIPA

LOC- 131/ 0/ 0 IINEMi-PRES IW-3

!1

*t

z:

4500000

4000000

3500000

3000000

2500000

2000000

1500000

1000000

I

S

I

S

S

S

S.

* S S ~S. -

I -

4.5

4.0

3.5

3.0

2.5

2.0

1.5

1.0

0.5

O0

0~

TZ

i •I II II tl tI I

0 20 40 60

REACTOR T[lE * SECONDS

FIGURE 176 INF 1 ISHARP, INF 2 ZEROGAP, INF 3 EXP

INTACT LOOP HOT LEG - PRESSURIZER

80 II

a
THE FOLLOI/UNG ARE PLOTTEO AGAINST REACTOR TIMlE

U PLENUIM AVG PRESSR ,PE-IUP-OOIA

WLIinEr'i th

t')

KEY

SYM N•IE UNITS BOL

- U PLENUtM AVG PRESSR ,N/I1**2

LOC= 501 O/ I IEtI-.PRUP (W=f

- U PLENUM AVG PRESSR ,N/tl**2

LOC= SO/ 0/ 1 1INEM=PRUP [tE=2

---PE-1UP-00IAMA

LOC. 1281 0/ 0 IINEt1-PRES ltF-3

0. 16E

0. 14E

0. 12E

0. IOE

0. SOE

0. 60E

0. 40E

0. 20E

fl. D0IW

O8

08

08

08

07

07

07

07

no

16

14

12

to

a

0~

6

4

2

0

0 20 40 60

REACTOR TIME , SECONDS

FIGURE 177 INF I ISHARPI INF 2 ZEROGAP, INF 3 EXP

UPPER PLENUM PRESSURE

so 100
. THE FOLLOWING ARE PLOTTED AGAINST REACTOR TIME

L[0 AXIAL VELOCITY ,FE-SLP-O01

Winnfri c hi

til

0'i

KEY

syiM BOL NAME UNITS

- LIO AXIAL VELOCITY HM/SEC

LOC= 50/ 3/ 1 MNEM=VL-Z INF=I

- LIO AXIAL VELOCITY "/tSEC

LOC= SO/ 3/ 1 ¶NEMVL-Z IhF=2

---. FE-5LP-O01 "I/SEC

LOC- 29/ 0/ 0 MNEMIFE IW-3

0 20 40 60 80 1O0

REACTOR TIME , SECONDS

FIGURE 178 INF I

LOWER

ISHARP, INF 2 ZEROGAPI INF 3 EXP

PLENUM LIQUID AXIAL VELOCITY
4 a

THE FOLLOVING ARE PLOTTED AGAINST REACTOR TItlE

LIO AXIAL VELOCITi ,FE-5UP-O00

1Winfr it h

t%)

O~h

KEY

SYll NAIE UNITS BOL

- LI0 AXIAL VELOCITY "H/SEC

LOC= 50/ 9/ I HNEM=VL-Z [IF=I

- LIO AXIAL VELOCITY H/SEC

LOC= 50/ 9/ I HNEfI=VL-Z IWF=2

--- FE-SMJ-001 a H/SEC

LOC- 31/ 0/ 0 flNEflFE [Wf-3

c..I

., II00

REACTOR TitlE , SECONDS

FIGURE 179 INF I ISHARP, INF 2 ZEROGAP, INF)3 EXP

UPPER PLENUM LIQUID AXIAL VELOCITY
THE FOLLO[ING ARE PLOTTED AGAINST REACTOR TIME

LIOUID TEMIPERATURE ,TE-IST-0O1

a'

KEY

Sml

B0L: NAMIE UN4 ITS

-LIDUJID TEMP~ERATRtNE *0EG.

LOCc 50/ Il/ 13 IINEII=TEIL INF~l

- LIOUID TEMPERATRWE *OEG.K

LOC= SO/ Il/ 13 tINEJ=ERL I}F=2

... TE-IST-001 , DEG.

LOC- 201/ 0/ 0 IINEII-TICL Iif-3

I-.

0' hi

D3

REACTOR TIHE ,. SECONDS

FIGURE 180 INF 1 [SHARP, INF 2 ZEROGAP, INF 3 EXP

DOWNCOMER LIbUIn TEMPERATURE AT 5.0 METRES
TilE FOLLOtIING ARE PLOTTED AGAINST REACTOR TIME

LIQUID TEMtPERATURE ,TE-IST-002

Win fr Ih

a%

4.13

KEY

SY NAME UN ITS

-LIQUID TEfW'ERATIJQE D(EG.IK

LOC: SO0/ ID/ 13 MNEtITEflL 1INF1

-LIQUID TEMP'ERATURE ,OEG.K

LOC= SO/ 10/ 13 ?INE"t=TEflL 11f=2

---TE-IST-002 , DEG. K

LOC. 202/ 0/ 0 rtIWf-T"CL Wf.3

'I

I-.

0 20 4N 0 60 N0 t00

REACTOR TIME , SECONDS

FIGURE 181 INF I ISHAPP, INF 2.ZEROGAPI, INF 3 EXP

DOO1NCOMER LIQOVI TEMPERATURE AT 4.2 METRES
THE FOLLOVING ARE PLOTTED AGAINST REACTOR T|ME

LUOUl TEI'PERATURE ,TE-IST-OO5

Winfr'ith

0~i

KEY

S" NAME UI*4TS

- LIOUZO TEMPERATURE OMK.P

LOC= SO/ 7/ 13 lMNEPIJEHL INEM

- LIOUID TEMP~ERATURE ,OEG.K

LOC= 50/ 71 13 t1NWi=TEML INF2

...TE-IST-005 OtEG.KZ

LOC- 205/ 0/ 0 HNEfHiTIICL INF-3

'U

CL

0 20. 40 60 80 100

REACTOR TitlE , SECONDS

F I GURE 182 INF I ISHARP, INF 2 ZEROGAP, INF 3 EXP

DOWNCOMER LIOUID TEMPERATURE AT 2.4 METRES
* w' -~. S

.4

- ~l..

THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIME

L1OUID TEMPERATURE ,TE-IST-012

lWinfrithl

Ml

KEY

SY NAMIE UITS 1

.-.LIQUID TEM1PERATRLIE ,DEG.K

LOC., 50/ 1/ 13 IIPfi=dEI1L IWE'2

-LfLIQIDl rEtIPERATR~sE O!EG.K~

LOC., 50/ 1/ 13 tINEtI:TEfL hE':2

--- E-IST-012 *DEG.KZ

LOC- 211/ 0/ 0 1lNEI-TI1CL (F~ft3

'ii

C)

REACTOR TIME , SECONDS

FIGURE 183 INF 1 ISHARP, INF 2 ZEROGAP,

DOWNCOMER LIQUID TEMPERATURE

INF 3 EXP

AT 0.3 METRES
I.

THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIME 1Win frt*rhl

til

NAJME UNITS

L PLENUll tilh/FLUX ~KG/ifS.q

L PLENUM liflh/FLUX KIG/Mo,~

,- L PLENUMI tffl/FLtJX ,KG/tiS-i

tn

r2:

mi

0

FIGURE 184 LINE I [SHARP, LINE 2 ZEROGAI

LOWER PLENUM MOMENTUM FLUX

ll.LINE 3 EXP

4.
THE FOLLOWING ARE PLOTTED AGAINST REACTOR TIME

CORE INLET MASS FLOW

l~3

4~.

d~h

NAME UNITS I

- CaiE tNLEr KlASS FUJOl,Ic(SEC

LOC= 50/ D/ I tlNEJ1=FLCI TNF.I

- CORE 11ILET KASS FLOV, IG/SEC

LOC= 50/ 0/ 1 MN~tll=FLCI (INF=2

ýl .h AllibilliH ill I-.

'Ll

U)

N.

-150

-200

0 20 40

REACTOR TIME

. 60 80 Ioo

, SECONDS

F I GURE 185 INF I ISHARP, INF 2 ZEROGAP

VESSEL GLOBALS
THE FOLLOWING ARE PLOTTED AGAINST REACTOR TIME

CORE OUTLET HASSFLOU

"I

t~J

o~I

SYII NAME LNITS

BOL

- CORE OUTLET hAS5FLOVKG/5EC

LOC= 50/ 0/ I tNEKl=FLCO f(F=t

- CORE OUTLET HASSFLOVKG/SEC

LOC= 50/ 0/ I I'IWEf=FLCO INF=2

C3

IUUJ)

to

0 20 40 60 80 I00

REACTOR TIME , SECONDS

FIGURE 186 INF I ISHARP, INF 2 ZEROGAP

VESSEL GLOBALS
'I.

ITlE FOLLOUI14G ARE PLOTTED AGAINST REACTOR TIIE

CORE LIQUID MASS

Winfrith

tj)

.P.

a%3

KEY

SYM NAM UNITS

BOL

- CORE LIQUID HIASS ,KG

LOC= 50/ 0/ I 1INEtILLHCR [NF=t

- CORE LIQUD MlIASS ,KG

LOC- 50/ 0/ 1 MINEJ:LHICR 11-2

C,

REACTOR TIMIE , SECONDS

FIGURE 187 INF I ISHARP, INF 2 ZEROGAP

VESSEL GLOBALS
THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIME

L PLENIi LIU VOL FRAC

1Winfrith

O4h

KEY

SYM NAME UNITS

BOL

- L PLENM LIO VOL FRAC,

LOC= 50/ 0/ 1 HIEMLFLP [W=I

0.0

0.9

- L PLEN" LIO VOL FRAC,

LOC= SO/ 0/ I tlINELiLFLP IW=2

0 20 40 60 80 100

REACTOR TIME , SECONDS

FIGURE .188 INF I ISHARP, INF 2 ZEROGAP

VESSEL GLOBALS

A
1.. 4'

• .. •....._

THE FOLOVIING ARE PLOTIED AGAINST REACTOR TIME

D'COiER LIU VOL FRAC

t~j

Lq'

- D'C OIER LI VOL FRAC,

LOC= 50/ 0/ I I1NEM=LFDC Ihf=I

- D'COMER L1O VOL FRAC,

LOC= SO/ 0/ I HINEfl=FDC INF=2 (.

0 20 40 . 60 00 100

REACTOR TIhE , SECONDS

FIGURE 189 INF I ISHARP, [NF 2 ZEROGAP

VESSEL GLOBALS
THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIME

CORE LIO VOL FRAC

WInfrithl

Xi

NAIE

- CORE LI1 VOL FRAC ,

LOC= 50/ 0/ 1 MNE--!LFCO [NF=I

- CORELIO VOL FRAC

LOCc 50/ 0/ 1 MNE'MzLFCO IFW=2

20

REACTOR TIhE , SECONDS

F I GURE 190 INF I ISHARP, INF 2 ZEROGAP

VESSEL GLOBALS

4,
V.--.

THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIME

VESSEL LIQUID MASS

lWinfr i r

t'3

I KEY

- VESSEL LIDUID MASS *KG

LOC= 50/ 0/ 1 IMNEM=LIVS [INf=

- VESSEL LIOUID IASS *lM

LOC= 50/ 0/ I lMNE2IIY.S INF=2

L3

0 20 40 60 80 100

REACTOR TIME , SECONDS

FIGURE 191 INF I ISHAPP, INF 2 ZEROGAP

VESSEL GLODALS
t'j

:E:

THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIME

TOT ROD HEAT FLUX

[WInfrith

KEY

SYM BOL NAME UNITS

TOT ROD HEAT FLUX WVATIS

LOC= 50/ 0/ 1 HNEM=ORDT If=I

- TOT ROD HEAT FLUX *VATTS

LOC- 50/ 0/ 1 INEII.OROT INF,2

I0

0. 60E

0. 55E

0. 50E

0. 45E

0. OE

0. 35E

tn 0. 30E

I--

>: 0.25E

0. 20E

0. 15E

0. IOE

0. 50E

0. OOE

0 20 40

REACTOR TIME

60

, SECONDS

80 100

FIGURE 192 INF I ISHARP, INF 2 ZEROGAP.

VESSEL GLOBALS
THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIMIE

TOT SLAB HEAT FLUX

Winfrithh

t'J

0~

KEY ... .

SYMl Ulmp INIT5

ElUL

- TOT SLAB HEAT FLUX ,VATTS

LOC= SO/ 0/ 1 HlNEl"=OSLT NF=t

TOT SLAB HEAT FLUX *VATTS

LOC= 501 0/ I 11NEi=OSLT INF=2

t'3

t)

O. 40E

0. 35E

0. 30E

0. 25E

0. 20E

0. ISE

0. 1OE

0. 50E

0. ODOE

00

08

08

08

08

08

08

07

00

0 20 40

REACTOR TIMlE

FIGURE 193 INF I ISHARPs INF 2 ZEROGAP

VESSEL GLOBALS

60

, SECONDS
THE FOILOUING ARE PLOTTED AGAINST REACTOR TIME

L PLENUlM AVG 110 TEll

uWInfr I t hl

til

KEY

SYli NAME UNIlTS 130L

- L PLENUM AVG LIO TEMJEG.IK

LOC= SO/ 0/ 1 1lNEH=7HLP DIW=l

- L PLENUM AVG LID IEM,DEG.K

LOC= 50/ O/ 1 MNE(flTtILP INF=2

0

Id

0~

60

REACTOR TIME , SECONDS

FIGURE 194 INF I ISHARP, INF 2 ZEROGAP

VESSEL GLOBALS

- a *
P. *.

THE FOLLOVIRG ARE PLOTTED AGA1I4ST REACTOR TItlE

CLADDINGi TE11P -FINETE-511O5-002

Iwinfrith

.N,.

KEY

cvm.

- CLAWOING TEMIP -Jt4EaOEG.K

LOC= 5O/ I/ I tff~lizHCL flfzl

- CLAMDING TEIIP -FINE,tEG.K

LaC= 50/ 1/ 1 I"tEI1T11CL INF=2

-- TF-"0f5-002 , BEG. K

LOC- 282/ 0/ 0 liNEII-TiCL [Wf-3

7S0

C,m

0 20 40 60 80 too 120

REACTOR TItE , SECONDS

F[GURE 195 INF I ISHARP, INF 2 ZEROGAP, INF 3 EXP

CENTRAL FUEL BUNDLE CLADDING TEMIPERATURES
THE FOLLOIlIHG ARE PLOTTED AGAINST REACTOR TitlE

CLADDING TEIP -FINETE-5G06-O11

lWin fr'i t

X~

K~EY

sy".

DOL NAME UNITS

-CLADDING TEMIP -FINE,IJEG.K

inC= 50/ 1/ S HNEM=THCL flf=I

- CLADDING TEJIP -FINE,DEG.K

LOC= SO/ 1/ 5 M"EP=ThiCL INF=2

TE-50-011 EG.K

1

LOC- 278/0/ 10 I1NEJ-TICL IWf.3

t'3 UIdl

0

0 20 40 - 0 80 100 120

REACTOR TIME , SECONDS

FIGURE 196 TNF I ISHARP, INF 2 ZEROGAP, INF 3 EXP

CENTRAL FUEL BUNDLE CLADDING TEMPERATURES
C

THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIME

CLADDING TEItP -FINE,TE-5106-021

lWin fri h1

.f~.

O~h

KEY

NAME UNITS 130L

- CLADDING TEMIP .-FINEDEG.IK

LOC= S0/ V/ 9 IINEfzTtICL 11f21

- CLADDING TEKiP -FINE,DEG.K

LUC= 50/ V/ 9 IIMTlTiCL ItF-2

-- TE-5106-021 *OCG.K

LOC. 2961 0/ 0 fINFtt-TttCL IWf.3

t'3

Lao d

iLt

Q

0 20 40 60 80 100 120

REACTOR TIME , SECONDS

FIGURE 197 INF I ISHARP, INF 2 ZEROGAP, INF 3 EXP

CENTRAL FUEL BUNDLE CLADDING TEHPERATURES
THE FOLLOUING ARE PLOTTED AGAINST REACTOR TIME

CLADDING TE1P -FINETE-5H06-024

1Win Erith]

ail

A.

KEY

SYM NAME UINTS BOL

- CLADDING TEIP -FINE,CtG.K

LOC 50/ 1I/ 10 HNEM=T"CL IF=I

- CLAWDING TEMIP -FINE,0EG.IK

LOCv SO/ 1/ 10 l1IEH=THCL INF=2

- - TE-5H06-024 . DE& K

LOC- 285/ 0/ 0 lINEI-TIICL rM?-3

(3IUl

C

K

FIGURE 198 INF I ISHARP, INF 2 ZEROGAP, INF 3 EXP

CENTRAL FUEL BUNDLE CLADDING TEMPERATURES
' ., -. -1.:

THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIME

CLADDING TEMP -FINE,TE-5104-027

Winrnf ichl

X'

KEY

80L

- CLAWDING lEWt -FINE, DEG. K

LOC= SO/ V/ 12 IINE"27MCL IW21=

1100

- CLADDING TEMP -FINE,0E0JK

LOC: S0/ V/ 12 MNf(H=TtCL NFF=2

-- TE-SI04-027 IDEG.K

LOC. 2931 0/ 0 liEtt-TttL INF-3J

Lii

0 20 .40 60 so 100 120

REACTOR TIME , SECONDS

FIGURE 199 'INF I [SHARP, INF 2 ZEROGAP, INF 3 EXP

CENTRAL FUEL BUNDLE CLADDIING TEMIPERATURES
THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIKE

CLADDING TEMP -FINETE-5007-031

1WIrfrith1

1000

N

t')

O~h

KEY

5TYh HMIE UNITS

BOL

- CLADDING TEMP -FINEIJEG.IK

LOC= 50/ I 13 HNEF_=TIICL INF=I

- CLADWING TEMP -FINE(OEG.K

LOC= 50/ I/ 13 MINEI=THCL INF=2

- - TE-5007--031 , VEG..IK

LOC- 271/ 0/ 0 IINEfl.TCL IWf-3

t~3 d

ta

REACTOR TIME , SECONDS

FIGURE 200 INF I ISHARP, INF 2 ZEROGAP, INF-3 EXP

CENTRAL FUEL BUNDLE CLADDING TEMPERATURES
4 . -. ,

THE FOLLOIVING ARE PLOTTED AGAINST REACTOR TIME

CLADDING TEl1P -FINETE-5106-039

jWlnfr' lhi

a'

IffA AUA1. i uvw I I

KEY

___i NAMIE UNJITS

-:-CLADDING TEWI -41NE1 DEM.I

LOCm 50/ V/15 IINEI~zTtCL IWIU,

950 .

- CLAMDING TEIP -FINE,DEG.IC

LOCa 50/ V/ 15 INEII:TiCL INF=2

- - TE-5106-039 ,DEG.K

LOC.- 297/ 0/ 0 tlWfllTlCL INF-3

900

850

800

750

La ",4 till IL

700

650

.1119.

I,

*1

I I

I I~

I i~

I ~

1111 i>*~Il

h' Ill ~ ~

'.. I

I I II I

"1 I

II

600

5501

500

450

Iii

"A't I

0 20 40 60 80 100 120

REACTOR TIME , SECONDS

FIGURE 201 INF I [SHARP, INF 2 ZEROGAP, INF 3 EXP

CENTRAL FUEL BUNDLE CLADDING TEIPERATURES
THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIME

CLADDING TEMP -FINE, TE-5104-43.8

1Winfr ithl

0%i

Ic3

KEY

syll

BOL NAMIE UNITS

(I

- CLAM~ING TEtiP -V1NEDEG.K

LOC= SO/ V/ 16 IINEii=TfCL 1Mxt

-- CLADDING TE11P -FINE, BEG. K

LOC= 50/ 4V 16 MNE"=TMCL INF=2

- - TE-5IO4-43.8 DOEG.K~

LOC- 294/ 0/ 0 tM~f-THCL tW-3

td

Iua

REACTOR TiME , SECONDS

FIGURE 202 INF I [SHARP, INF 2 ZEROGAP, INF 3 EXP

CENTRAL FUEL BUNDLE CLADDING TEMPERATURES
THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIME

CLADDING TE'tP -F[NE,TE-SHO5-049

I win fr i t h

tIj

KEY

BL NAMIE W i Y5

- CLADDING TEMP -FINE,I)EGA.

LCC= 50/ 1/ 1? lINE1=THCL IW'=1

850

- CLADDING TEMP -FINEUIEG.K

LOC= 50/ I/ 17 INEtTI=TCL I[F=2

- - TE-5HD5-049 , DEG. K~

LOC- 284/ 0/ 0 HNIIN-ITIICL Ilf.3

Iii

C

0 20 2 4N 60 80 100 120

REACTOR TIME SECONDS

FIGURE 203 INF I ISHARP, [NF 2 ZERDOAP, INF 3 EXP

CENTRAL FUEL BUNDLE CLADDING TEMPERATURES
TIE FOLLOUING ARE PLOTTED AGAINST REACTOR TitlE

CLADDING TEMP -FINETE-5G06-062

Win fr i c h

X

0%

otb

KEY

- CLADDING TEMIP -FINEDEG.IK

LOCs SO/ 1/ 20 flNEtt1TCL hNFm1

- CLADDING TEIIP .-FINE,DEG.K

LOC= SO/ 1/ 20 ?INEH=TtCL [?f=2

- - TE-5G06-462 - , EG. K

LOC. 281/ 0/ 0 MNHIM~l.fCL IW-3

ld

cl

REACTOR TItlE , SECONDS

FIGURE 204 INF 1 ISHARP, INF 2 ZEROGAP, INF 3 EXP

CENTRAL FUEL BUNDLE CLADDING TEMPERATURES
V 4. - K

THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIHE

ROD CENTRE TEIIP-FINE,TC-5DO7-27

TC-501 0-27

,TC-5009-27

Wlinfr I thj

KEY I

s"', NA UN~ITS

BOL. NAME

- ROD CENTRE TE11P-FINE, BEG. K

LOC= 50/ 1/ 12 RfNEtf=TRIRC 1WF=I

- ROD CENTRE TEI'P-FINEDEG.K

LOC= SO/ I/ 12 IINEI=TtIRC INF=2

... C-5007-27 DG

LDC- 101/ 0/ 0 flNEII-TIIC [W-3

- - TC-5009-2? E.

LOC= 169/ 0/ 0 IiNEfldTiRC INFu3

- - TC-SDtO-27 DDEG.K

LOC- 1701/ 0/ 0 IINEtf-THRC INF=3

d

I-,,

T

i

a 20 40 60 80. 100 120 1 I

REACTOR TIME , SECONDS

FIGURE 205 INF I ISHARP, INF 2 ZEROGAP, INF 3 EXP

CENTREL[NE FUEL TEMPERATURE
THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIHE

CLADDING TEMlP -FINE,TE-2GI4-OI1 I

WinfrI th

twi

0'.

KEY

SYm NAME UNITS

BOL

- CLADDING TE.MP -FINEDEG.Ir

LOC= 50/ 5/ 5 ,NE?'=THCL INF=!

- CLADDING TEMIP .-FINEDEG.K

LOC- 50/ 5/ 5 liNEMli=CL INF=2

.... TE-2GI4-OI, DEG.K

LOC- 220/ 0/ 0 IiNEM-ThlCL INF-3

4:-

t13 Iii

lm

0 20 40 60 80 100 120

REACTOR TI[E , SECONDS

FIGURE 206 INF I ISHARP, INF 2 ZEROGAPo INF

FUEL ROD CLADDING TEMPERATURES -

3 EXP

PERIPHERAL BUNDLES

W V
V * 4 4. S

THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIME

CLADDING TE11P -FINETE-2HI3-021

IWinfrith

Ni

0'i

Ni

(A

KEY

SYII NAME UI*TS 80L________

-CLADDING TEMIP -FINE,DECLK

LOC= 50/ 51 9 IMtEt=TflCL IWE=I

- CLADDING TEMP -FINEDEGAK

LOC= 50/ 5/ 9 IINEtizTICL INF=2

---TE-2H13-021 aOEG.KZ

LOC- 2251 0/ 0 tfl~t1.TflL Iff-3

'Ii

Q

.REACTOR TIME , .SECONDS

FIGURE 20? INF I [SHARP, INF 2 ZEROGAP, INF 3 EXP

FUEL ROD CLADDING-TEMPERATURES - PERIPHERAL BUNDLES
ITHE FOLLOVING ARE PLOTIED AGAINST REACTOR TIME

CLADDING TEMP -FINE,TE-2GI4-030

jWinfr'thh

t?1

a'

KEY

SYlt

BOL NAME ITS

CLADDING rEtMP -FINE,DEG.IK

LOC: SO/ 5/ 13 liNEtI=TflCL I•f=t

- CLADDING TEIiP -FINE,DEG.K

LOC= SO/ 5/ 13 MNEH=THCL INF=2

7uur I I

---TE-2tGI4-030 E.

LOC- 221/ 0/ 0 flNEIM-THCL. hNF-3

850

800

750

700

650

600

550

.:-

2- .

Idl v

* *5 * *5

* *5 * IS g Dj a 55

* Si it, a' *g~

I'.- j~*'*

I I ~ ID *' I

* a I * a I

1!

S. S. S

Sjy-----

500 I

450 .

i. nn a I |

0 20 40 60 80 100 120

REACTOR TIME , SECONDS

FIGURE 208 INF I ISHARP, INF

FUEL ROD CLADDING

2 ZEROGAP, INF

TEMPERATURES -

3 EXP

PERIPHERAL BUNDLES
THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIME

CLADDING TEMiP -FINETE-2114-039

1Win fr I th]

Ln~

KEY

UUL. NAHE UNITS

CLAMDING TEnIIP -FINEIDEG.K

LOC2 50/ 8/ 15 1INEl-7HCL IWf=I

- CLADDING TEtIP -FINEDEG.lK

LOCut SO/ 6/ 15 INDI=THCL INF=2

---TE-2t114-39 iOEG.K

LOC. 229/ 0/ 0 II~li-TtiCL [IW-S

d

'Ii a

0 20 40 60 80 100 120

REACTOR TIME , SECONDS

FIGURE 209 INF I ISHARP, INF 2 ZEROGAP, [NF 3 EXP

I FUEL ROD CLADDING TEMPERATURES - PERIPHERAL BUNDLES
THE FOL.LOING ARE PLOTTED AGAINST REACTOR TIME

CLADDING TEMP -FINETE-2HI3-0O49

WIn nfrith

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SYh NAME UNITS

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- CLAWDING TEIIP -FINEDEG.K

LOC= 50/ S/ 17 MNEII4=TICL fNF=I

- CLADDING 'EIP -FINEDEG.K

LOC= 50/ 5/ 17 MNEMI=TflCL If=2

---- TE-2H13-049 ,DEG.K

LOC. 224/ 0/ 0 IMNEM-TMCL INFW3

0' lii

C

REACTOR TIME SECONDS

FIGURE 210 INF 1 ISHARP, INF 2 ZEROGAP, INF 3 EXP

FUEL ROD CLADDING TEMPERATURES - PERIPHERAL BUNDLES
, 6 .. ..

THE FOLLOV|IG ARE PLOTTED AGAINST REACTOR TIHE

CLADDING TEMiP -FIHETE-4GI4-OI1

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---TE-GI',-0I1 DIEr.K

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LEA

C

0 20 40 60 80 100 120

REACTOR TIME , SECONDS

FIGURE 211 INF I ISHARP, INF 2 ZEROGAP, INF 3 EXP

FUEL ROD CLADDING TEMPERATURES - PERIPHERAL BUNDLES
L.. -

THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIME

CLADDING TEMP -FINE,TE-4G08-021

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---TE-'4GO8-021 *DEG.K

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'Ii

REACTOR TIME , SECONDS

FIGURE 212 INF I [SHARP, INF 2 ZEROGAP, INF 3 EXP

FUEL ROD CLADDING TEMPERATURES - PERIPHERAL BUNDLES
.4 a"

TIE F(LLOVING ARE PLOTTED AGAINST REACTOR TitE

CLAWDING TEMP~ -FINE,TE-4HIIt-028

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KEY

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---TE-4HII-028 ,DEG.K

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4001•

0 20 40 60 60 I O0 120

REACTOR TIME ,SECONDS

FIGURE 213 INF I fSHARPt INF 2 ZEROGAP, INF 3 EXP

FUEL ROD CLADDING TEM'PERATURES - PERIPHERAL BUNDLES
THE FOLLOVING ARE PLOTTED AGAINST REACTOR TIME

CLADDING TEIP -FINETE-414-039

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SYM BOL NAIME UNITS

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- CLAW=IN TEMP .FINE,DEG.K

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REACTOR TIME , SECONDS

FIGURE 214 INF I ISHARP, INF 2 ZEROGAP, INF

FUEL ROD CLADDIT"' TEMPERATURES -

3 EXP

PERIPHERAL BUNDLES

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---. TE-6G14-011 *IG.K

LOC- 329/ 0/ 0 lIJttfTICL IW-3

hii

0'

0 20 - 40 60 80 too 120

REACTOR TIME , SECONDS

FIGURE 215 INF I [SHARP, [NF

FUEL ROD CLADDING

2 ZEROGAP, INF

TEMPERATURES -

3 EXP

PERIPHERAL BUNDLES
THE FOLLOVING ARE PLOTTED AGAINST REACTOR IM[E

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li3

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REACTOR TIME , SECONDS

FIGURE 216 INF I ISHARP, INF 2 ZEROGAP, INF 3 EXP FUEL ROD CLADDING TEMPERATURES - PERIPHERAL BUNDLES
of "

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LOC- 335/ 0/ 0 IIN"f-TtCL IW-3

0 20 40 60 .80 . 100 120

REACTOR TIME , SECONDS

FIGURE 217 INF I ISHARP, INF 2 ZEROGAP, INF 3 EXP

FUEL ROD CLADDING TEMPERATURES - PERIPHERAL BUNDLES
THE FOILOIVING ARE PLOTTED AGAINST REACTOR TIME

CLADDING TEM'P -FINE,TE-6114-039

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---- TE-6114-039 ,DEG.K

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0 20 40 60 80 100 120

REACTOR TItE SECONDS

FIGURE 218 INF I ISHARP, INF 2 ZEROGAP, INF 3 EXP

FUEL ROD CLADDING TEMPERATURES - PERIPHERAL BUNDLES
LI

THE FOLLOUING 0ARE PLOITED AGAIkNST REACTOR TIME

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REACTOR TIIlE , SECONDS

FIGURE 219 INF I ISHARP, INF 2 ZEROGAP, INF 3 EXP

FUEL ROD CLADDING TEMPERATURES - PERIPHERAL BUNDLES

PWR EMT TRAN1SFER AND HYDI:ZADI WRK~IM GFJP

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BIBLIOGRAPHIC DATA SHEET

" . " ... NUREG/IA-0027

-- -------------------.. ; AEEW-M 2464

TRAC-PF1/MOD1 Calculations of LOFT Experiment LP-02-6 -

April 1992 4 ,z-• -', , ''.. -.

A4682

S. AUTHORIS. 6 TYDE 0' 1E1C=-

Technical

P. Coddington, C. Gill 7 PERIOD CC', ' .EZ

8. PER FO RMI NG 0ORGAN IZATION - NAME AND ADDR ESS #to NRtC. VrQ,*d 0,-,lto. 00,,ce or Rego,O V.$ fuclra, Regu.loy, Cam.,",oA. e^d mad,n,,g 'Odl~e's 0¢~,,r, ,, Aan, and mf.l•n*g add*res.1

Winfrith Technology Centre

United Kingdom Atomic Energy Authority

Winfrith, Dorchester

Dorset, England DT 28 DH

9. SPONSORING ORGANIZATION - NAME AND ADDRESS III NRC. ryve "Si." a, adoroe ,f oron-cf o'o..ae NRC D-..on. Offie. ao Regeo. US. Nucleet Repsatery CO-SMlon and mailing eddres&)

Office of Nuclear Regulatory Research

U. S. Nuclear Regulatory Commission

Washingtog, DC 20555

10. SUPPLEMENTARY NOTES

1I. ABSTRACT 20 words or tu

Experiment LP-02-6 was the First Large Break (200% Double Ended Cold Leg) Loss-ofCoolant Accident (LOCA) Experiment carried out in the Loss-Of Fluid Test (LOFT)

Facility under the auspices of the Organization For Economic Cooperation and

.Development (OECD).

This report contains a comparison of the results of experiment LP-02-6 with those

of TRAC-PF1/MOD1 calculation.

12. KEY WORDS/DESCR!PTORS ILl -oA* orphe/ws tlte •I/t anise murhEVto locating fn. Frorr.l 13. AVAILA8ILITY STATEMENT

ICAP Program, TRAC-PF1, LP-02-6, LOCA,' Large Break Unlimited

14. SECuRITY CLASSIFICATION

1 This Pnuj

Unclassified

I, Th~sFamRer)?

Unclassified

IS. NUMBER OF PAGES

IS. PRICE

NRC FORM-335 12-89)
TAG

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