Upload
garry-harvey
View
216
Download
1
Embed Size (px)
Citation preview
1DEN /Valrhô /Centrale Phénix NEA 8th Information Exchange Meeting Las Vegas, 9th-11th of November 2004
PHENIX:
The irradiation programme for transmutation experiments
J. Guidez
Head of PHENIX reactor
2DEN /Valrhô /Centrale Phénix NEA 8th Information Exchange Meeting Las Vegas, 9th-11th of November 2004
GENERAL DESIGN of the PLANT
3DEN /Valrhô /Centrale Phénix NEA 8th Information Exchange Meeting Las Vegas, 9th-11th of November 2004
PLANT DATA
First criticality: 31st August 1973
First connection to the grid: 13th December 1973
Commercial operation: 14th July 1974
Nominal Power: 563 MWth (250 MWe)
Since 1993 Power limited to 350 MWth (145 MWe),
on two secondary loop operation.
Total number of Equivalent Full Power Days: 3990
Total operating hours: 106 000 h
Gross electrical output: 23 123 400 MWh
4DEN /Valrhô /Centrale Phénix NEA 8th Information Exchange Meeting Las Vegas, 9th-11th of November 2004
6 years of work in two phases from 1994 to 1997 and 1999 to 2003, separated by one operating cycle.
250 million € of studies and renovation works
5000 contract entered into,
350 sub-contracting companies
4500 agents working for the sub-contractors (up to 700 per day)
[PHENIX staff : 210 CEA + 70 EDF]
PLANT LIFETIME EXTENSION WORK
5DEN /Valrhô /Centrale Phénix NEA 8th Information Exchange Meeting Las Vegas, 9th-11th of November 2004
PLANT OPERATING DIAGRAM 2004
52 ème cycle52 ème cycle
2004
350300
200
OctJanvier Février Mars Avril Mai Juin Juillet Août Sept Nov Déc
100
AT2
51th cycle51th cycle
AM1
51th cycle: 210 Days at nominal power 131 EFPD
Availability factor: 94%Load factor: 85%
Power operation
Operation schedule
6DEN /Valrhô /Centrale Phénix NEA 8th Information Exchange Meeting Las Vegas, 9th-11th of November 2004
FUTURE OPERATION of the PLANT
80% Load factor
1 2 3 4 5 6 7 8 9 10 11 12 1 2 3 4 5 6 7 8 9 10 11 12 1 2 3 4 5 6 7 8 9 10 11 12
51 - 2 52-1 53-1
2004 2005 2006
1 2 3 4 5 6 7 8 9 10 11 12 1 2 3 4 5 6 7 8 9 10 11 12 1 2 3 4 5 6 7 8 9 10 11 12
53-2 54-1
54-2 55-1 55-2 56-1 56-2
2007 2008 2009
6 cycles of 120 EFPD
equivalent to about 5.5 years of operation
52-2
7DEN /Valrhô /Centrale Phénix NEA 8th Information Exchange Meeting Las Vegas, 9th-11th of November 2004
EXPERIMENTAL CONDITIONS AT PHENIX
Fast flux (n/cm2.s)
Thermal flux (n/cm2.s)
Dose rate
PWR power reactor
1.3.1014 0.9.1014 2 dpa/year
OSIRIS, HFR, BR2 type research reactor …
2 to 4.1014 4 à 7.1014 3 dpa/year
Phénix reactor
2.5.1015 4.4 . 10 15
18 dpa/6-month
cycle Type 1
moderate flux*3.6.1015 12 dpa/
cycle
Type 2 moderate flux*
1.5.1015 3.7.1013 4 dpa/6-mont cy
cle
COMPARISON OF NEUTRON FLUX
* Types 1 and 2 correspond to the type of moderating carrier used : 1: 11B4C , 2: CaHx
8DEN /Valrhô /Centrale Phénix NEA 8th Information Exchange Meeting Las Vegas, 9th-11th of November 2004
TEMPERATURE
Core inlet/outlet: 380/550°C
Device developed for material irradiation up to 1000°C
MEASUREMENTS
Sodium inlet/outlet Temperature
Sodium sampling at S/A outlet
Argon gas blanket analysis
EXPERIMENTAL CONDITIONS AT PHENIX
9DEN /Valrhô /Centrale Phénix NEA 8th Information Exchange Meeting Las Vegas, 9th-11th of November 2004
EXPERIMENTAL RIG AND CARRIER
EXPERIMENTAL CONDITIONS AT PHENIX
10DEN /Valrhô /Centrale Phénix NEA 8th Information Exchange Meeting Las Vegas, 9th-11th of November 2004
PHENIX EXPERIMENTAL TRANSMUTATION PROGRAMME
General irradiation data acquisition Neutronic data measurements
Fuel irradiation for homogeneous transmutation mode
Target irradiation for heterogeneous transmutation mode
Constituent materials (Inert matrices, moderators) Irradiation of actinide-based compounds (primarily Americium) Irradiation of targets containing long-lived fission products (Technetium 99)
Irradiation of high Pu content fuel
Fuel irradiation for future systems(dedicated critical or sub-critical transmutation systems, GFR...)
11DEN /Valrhô /Centrale Phénix NEA 8th Information Exchange Meeting Las Vegas, 9th-11th of November 2004
1
101 111
201
211
191
181
171
161 151
141
121 131
71
91
81 70
110
200
210
190
170
160 150
140
120 130
90
80
100
61
51
41 31
21 20
11 10
2
102 103 112
202
212
192
182
172
162
142
122 132
72
92
82
62
52
42 32
22
12
3
163
113
203
213
193
183
173
153
143
123 133
73
93
83
63
53 43
33 34
23
13
4
104
164
134
114
204
214
194
184
174
154
144
124
74
94
84
64
54 44
24
14
5
105
165
135
115
205
215
195
185
175
155
145
125
85
75
95
65
55 45
35
25
15
6
106
176
166
136
116
206
216
196
186
156
146
126
86
76
96
66 56
46
36
26
16
7
107
177
167
137
117
207
217
197
187
157
147
127
87
77
97
67 57
47
37
27
17
8
108
188 198
208
178
168
158
138 148
118 128
88
78
98
68 58
48
38 40
28
18
9
109
199
209
189
179
169
159 149
139
119 129
89
79
99
69 59 60
49 50
39
29 30
19
Profil-R pins
Reference standard pin
PROFIL-R SUB-ASSEMBLY
Measurement of actinides and fission products cross sections in fast (PROFIL-R) and moderated (PROFIL-M) neutron flux
PROFIL-R container
Cask
Body
Isotope
Height 10 mm
Containers
Spacers PROFIL-R pins
12DEN /Valrhô /Centrale Phénix NEA 8th Information Exchange Meeting Las Vegas, 9th-11th of November 2004
71U 19Pu 10Zr
67U 19Pu 10Zr 2A.M. 2T.R.
66U 19Pu 10Zr 5A.M.
61U 1 9Pu 10Zr 5A.M. 5T.R.
Core center plane
1 2 3
METAPHIX: Irradiation of Actinides diluted in metal fuel (UPuZr+MA+RE)Contract with ITU Karsrhue for CRIEPI
METAPHIX: Irradiation of Actinides diluted in metal fuel (UPuZr+MA+RE)Contract with ITU Karsrhue for CRIEPI
1 2
34
5
6 7
8
9
101112
13
14
15
16 17 18
19
1
2
3
4
5
6
7
8
9
10
1112
1314
15
1617
1819
2021
2223
24
25
26
27
28
29
30313233
34
35
36
37
38
39 40 41 42
StdCoeur 1
StdCoeur 1
StdCoeur 1
StdCoeur 1
StdCoeur 1
StdCoeur 1
StdCoeur 1
StdCoeur 1
StdCoeur 1 M ET-1
M ET-2
M ET-3
StdCoeur 1
StdCoeur 1
StdCoeur 1
StdCoeur 1
StdCoeur 1
StdCoeur 1
StdCoeur 1
1
2
444
4
4 4 4
4
4
4
444
4 4
4
3
Standard pins
Experimental pins
Capsule contentCapsule content
3 capsules containing
3 pins each
3 capsules containing
3 pins each
HOMOGENEOUS TRANSMUTATION EXPERIMENT
13DEN /Valrhô /Centrale Phénix NEA 8th Information Exchange Meeting Las Vegas, 9th-11th of November 2004
INERT MATRIX TESTING
MATINA 1A: re-irradiation of MATINA 1 experiment dismantled in 1996 (first selection of most promising inert matrices for heterogeneous transmutation).
MATINA 2-3 (scheduled in 2005):Testing of:
CERCER targets with a MgO matrix and micro-dispersed and macro-dispersed particles,
new materials (pyrochlore Ce2Zr2O7 and yttriated zirconia ZrYO compounds)
14DEN /Valrhô /Centrale Phénix NEA 8th Information Exchange Meeting Las Vegas, 9th-11th of November 2004
ECRIX EXPERIMENTS: OBJECTIVES
First experiment of Am transmutation in specific target in a fast reactor
Testing two concepts of « once trough » transmutation by using local moderation spectrum:
1. 11B4C : ECRIX-B
2. CaH2 : ECRIX-H
1. Fuel fabrication process (metallurgy powder) which can be applied to the industrial scale
2. Development of fabrication and characterisation techniques
3. Fabrication of 100 pellets
4. Property measurements*
5. Irradiation started at Phenix* Collaboration with
ITU/Karlsruhe
15DEN /Valrhô /Centrale Phénix NEA 8th Information Exchange Meeting Las Vegas, 9th-11th of November 2004
ECRIX B and H : Transmutation of Americium in MgO inert matrix, pins located inside special moderating carriers)
ECRIX : moderator sub-assembly and capsule cross section
ECRIX EXPERIMENTS: SUB-ASSEMBLY DESIGN
16DEN /Valrhô /Centrale Phénix NEA 8th Information Exchange Meeting Las Vegas, 9th-11th of November 2004
Moderator CaHx thickness 9,5 mmheight 300 mm
Steel spacers
DMC 2
Capsule KMCSteel cylinder
DMC 2 MODERATOR CARRIER AND CAPSULE
17DEN /Valrhô /Centrale Phénix NEA 8th Information Exchange Meeting Las Vegas, 9th-11th of November 2004
TRANSMUTATION RATES IN PWR COMPARED TO PHENIX MODERATED FLUX
Am éricium target in PWR : - Evolution of compositions - Evolution of Am transmutation rate et global f ission rate
0
10
20
30
40
50
60
70
80
90
100
0 100 200 300 400 500 600 700 800 900 1000 1100 1200 1300 1400 1500 1600 1700 1800 1900 2000
EFPD
%PuAmCmtaux de transmutation Amtaux de fission
Technological limit
At technological limit one obtains : fission rate ~25% transmutation rate ~90% remaining mass contents : 55% Pu, 10%Am et 10% Cm
Americium target in PHENIX moderating spectrum : - Evolution of compositions - Evolution of Am transmutation rate and global f ission rate
0
10
20
30
40
50
60
70
80
90
100
0 100 200 300 400 500 600 700 800 900 1000
1100
1200
1300
1400
1500
1600
1700
1800
1900
2000
EFPD
%
PuAmCmtaux de fissiontaux de transmutation Am
Technological limit (200 DPA NRT)
At technological limit one obtains :f ission rate ~95% transmutation rate ~100%remaining mass contents :3% Pu, 0%Am et 2% Cm
18DEN /Valrhô /Centrale Phénix NEA 8th Information Exchange Meeting Las Vegas, 9th-11th of November 2004
ECRIX EXPERIMENTS: PIN DESIGN
Cladding
UO2 pellets
UO2 pellets
Fissile columnwith americiumtarget - pellets
500 µm
Porosités en noir
AmOx en blanc
MgO en gris
Black elements : porosities
White elements : AmOx particle
Grey area : magnesia
Microstruture : CERCER Microdispersed type
Inert matrix : MgO
Fuel Particles: AmOx
Am content : 0,7g of Am/cm3
Height density : 97%
19DEN /Valrhô /Centrale Phénix NEA 8th Information Exchange Meeting Las Vegas, 9th-11th of November 2004
LLFP TRANSMUTATION: ANTICORP 1
Capsule: 3 pins with two pieces of 99Tc metal Moderator carrier Transmutation rate target: 25%
20DEN /Valrhô /Centrale Phénix NEA 8th Information Exchange Meeting Las Vegas, 9th-11th of November 2004
Irradiation of high Pu content fuel
To assess: Thermal-mechanical behaviour of the pin Radial Pu redistribution Cladding Internal corrosion Reprocessing
2 pins: 45% Pu /(U+Pu) enrichment pellets with
17 driver fuel pins in a capsule
Target burn-up : 10 at%
CAPRIX 1 EXPERIMENT
21DEN /Valrhô /Centrale Phénix NEA 8th Information Exchange Meeting Las Vegas, 9th-11th of November 2004
CORE LOCATION OF TRANSMUTATION EXPERIMENTS
22DEN /Valrhô /Centrale Phénix NEA 8th Information Exchange Meeting Las Vegas, 9th-11th of November 2004
Optimisation of target for Americium transmutation CAMIX (Composé d’AMéricium dans PhénIX) :
optimisation of actinide compound
COCHIX (Conception Optimisée vis-à-vis des miCrostructures dans pHénIX) :testing of new microstructures (macromasses) dispersed in inert matrix
MATINA 2-3testing of CERamics/CERamics targets with a MgO matrix and macrodispersed particles and of new materials
Fuel for future systems FUTURIX/FTA (FUels for Transmutation of transURanien elements in
PhénIX/Fortes Teneurs en Actinides
testing of Metal, nitride, CER/MET, CER/CER fuels with high TRU content
Collaboration with US/DOE, ITU, CRIEPI
three further experiments planned (fuel and materials for Gas-cooled FR)
FUTURE EXPERIMENTS
23DEN /Valrhô /Centrale Phénix NEA 8th Information Exchange Meeting Las Vegas, 9th-11th of November 2004
Successful re-start after a major safety upgrading of the PHENIX plant ( the unique fast breeder reactor in Europe )
(Availability factor 94% in 2004)
Transmutation experimental programme in progress for: Americium , Technetium 99 ,inert matrix for heterogeneous
transmutation(ECRIX, ANTICORP, MATINA) Homogeneous transmutation (METAPHIX ) High PU content fuel (CAPRIX) Neutronic datas (PROFIL)
which shall provide a validation of a wide range of concepts
Preparation of future experiments for the next cycles.
CONCLUSIONS