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RERTR Publications:
Foreign Research Reactor Spent Nuclear Fuel
ANL/RERTR/TM-26
Table 3. MTR Fuel 45% Enrichment
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MTR Fuel |
45% |
Enrichment |
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200 |
g U-235 |
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U-235 Burnup, % |
0 |
5 |
10 |
20 |
30 |
40 |
50 |
60 |
70 |
80 |
U-235 Burned, g |
0 |
10 |
20 |
40 |
60 |
80 |
100 |
120 |
140 |
160 |
U-234 |
0 |
0 |
0 |
0 |
0 |
0 |
0 |
0 |
0 |
0 |
U-235 |
200 |
190 |
180 |
160 |
140 |
120 |
100 |
80 |
60 |
40 |
U-236 |
0 |
2 |
3 |
6 |
10 |
13 |
16 |
19 |
21 |
24 |
U-238 |
244 |
244 |
244 |
243 |
242 |
241 |
240 |
239 |
237 |
236 |
U |
444 |
436 |
427 |
409 |
391 |
374 |
356 |
337 |
319 |
300 |
Np-237 |
0 |
0.0 |
0.0 |
0.0 |
0.1 |
0.2 |
0.3 |
0.4 |
0.6 |
0.8 |
Np |
0 |
0.0 |
0.0 |
0.0 |
0.1 |
0.2 |
0.3 |
0.4 |
0.6 |
0.8 |
Pu-238 |
0 |
0.0 |
0.0 |
0.0 |
0.0 |
0.0 |
0.0 |
0.1 |
0.1 |
0.2 |
Pu-239 |
0 |
0.4 |
0.7 |
1.3 |
1.7 |
2.0 |
2.3 |
2.4 |
2.3 |
2.2 |
Pu-240 |
0 |
0.0 |
0.0 |
0.1 |
0.2 |
0.3 |
0.5 |
0.6 |
0.8 |
0.9 |
Pu-241 |
0 |
0.0 |
0.0 |
0.0 |
0.0 |
0.1 |
0.2 |
0.2 |
0.3 |
0.4 |
Pu-242 |
0 |
0.0 |
0.0 |
0.0 |
0.0 |
0.0 |
0.0 |
0.0 |
0.1 |
0.2 |
Pu |
0 |
0.4 |
0.7 |
1.4 |
2.0 |
2.5 |
2.9 |
3.3 |
3.6 |
3.8 |
Am-241 |
0 |
0.0 |
0.0 |
0.0 |
0.0 |
0.0 |
0.0 |
0.0 |
0.0 |
0.0 |
Am |
0 |
0.0 |
0.0 |
0.0 |
0.0 |
0.0 |
0.0 |
0.0 |
0.0 |
0.0 |
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MTR Fuel |
45% |
Enrichment |
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300 |
g U-235 |
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U-235 Burnup, % |
0 |
5 |
10 |
20 |
30 |
40 |
50 |
60 |
70 |
80 |
U-235 Burned, g |
0 |
15 |
30 |
60 |
90 |
120 |
150 |
180 |
210 |
240 |
U-234 |
0 |
0 |
0 |
0 |
0 |
0 |
0 |
0 |
0 |
0 |
U-235 |
300 |
285 |
270 |
240 |
210 |
180 |
150 |
120 |
90 |
60 |
U-236 |
0 |
3 |
5 |
10 |
15 |
19 |
24 |
29 |
33 |
37 |
U-238 |
367 |
366 |
365 |
364 |
362 |
361 |
359 |
357 |
355 |
352 |
U |
667 |
654 |
640 |
614 |
587 |
560 |
533 |
505 |
477 |
449 |
Np-237 |
0 |
0.0 |
0.0 |
0.1 |
0.2 |
0.4 |
0.6 |
0.9 |
1.2 |
1.5 |
Np |
0 |
0.0 |
0.0 |
0.1 |
0.2 |
0.4 |
0.6 |
0.9 |
1.2 |
1.5 |
Pu-238 |
0 |
0.0 |
0.0 |
0.0 |
0.0 |
0.0 |
0.1 |
0.1 |
0.2 |
0.3 |
Pu-239 |
0 |
0.6 |
1.2 |
2.2 |
2.9 |
3.4 |
3.8 |
3.9 |
3.8 |
3.6 |
Pu-240 |
0 |
0.0 |
0.0 |
0.2 |
0.3 |
0.6 |
0.8 |
1.0 |
1.2 |
1.4 |
Pu-241 |
0 |
0.0 |
0.0 |
0.0 |
0.1 |
0.2 |
0.3 |
0.5 |
0.6 |
0.7 |
Pu-242 |
0 |
0.0 |
0.0 |
0.0 |
0.0 |
0.0 |
0.0 |
0.1 |
0.2 |
0.3 |
Pu |
0 |
0.6 |
1.3 |
2.4 |
3.4 |
4.2 |
5.0 |
5.6 |
6.0 |
6.3 |
Am-241 |
0 |
0.0 |
0.0 |
0.0 |
0.0 |
0.0 |
0.0 |
0.0 |
0.0 |
0.0 |
Am |
0 |
0.0 |
0.0 |
0.0 |
0.0 |
0.0 |
0.0 |
0.0 |
0.0 |
0.0 |
Table 3. MTR Fuel 45% Enrichment (conti.)
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MTR Fuel |
45% |
Enrichment |
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400 |
g U-235 |
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U-235 Burnup, % |
0 |
5 |
10 |
20 |
30 |
40 |
50 |
60 |
70 |
80 |
U-235 Burned, g |
0 |
20 |
40 |
80 |
120 |
160 |
200 |
240 |
280 |
320 |
U-234 |
0 |
0 |
0 |
0 |
0 |
0 |
0 |
0 |
0 |
0 |
U-235 |
400 |
380 |
360 |
320 |
280 |
240 |
200 |
160 |
120 |
80 |
U-236 |
0 |
3 |
7 |
14 |
20 |
27 |
33 |
39 |
45 |
50 |
U-238 |
489 |
488 |
487 |
485 |
482 |
480 |
477 |
474 |
471 |
467 |
U |
889 |
871 |
854 |
818 |
782 |
746 |
710 |
673 |
636 |
597 |
Np-237 |
0 |
0.0 |
0.0 |
0.2 |
0.4 |
0.6 |
1.0 |
1.4 |
1.8 |
2.4 |
Np |
0 |
0.0 |
0.0 |
0.2 |
0.4 |
0.6 |
1.0 |
1.4 |
1.8 |
2.4 |
Pu-238 |
0 |
0.0 |
0.0 |
0.0 |
0.0 |
0.1 |
0.1 |
0.2 |
0.3 |
0.5 |
Pu-239 |
0 |
0.9 |
1.8 |
3.2 |
4.2 |
4.9 |
5.4 |
5.5 |
5.4 |
5.0 |
Pu-240 |
0 |
0.0 |
0.1 |
0.3 |
0.5 |
0.8 |
1.1 |
1.4 |
1.6 |
1.9 |
Pu-241 |
0 |
0.0 |
0.0 |
0.1 |
0.2 |
0.3 |
0.6 |
0.8 |
1.0 |
1.1 |
Pu-242 |
0 |
0.0 |
0.0 |
0.0 |
0.0 |
0.0 |
0.1 |
0.2 |
0.3 |
0.5 |
Pu |
0 |
0.9 |
1.9 |
3.5 |
4.9 |
6.2 |
7.2 |
8.1 |
8.7 |
9.1 |
Am-241 |
0 |
0.0 |
0.0 |
0.0 |
0.0 |
0.0 |
0.0 |
0.0 |
0.0 |
0.0 |
Am |
0 |
0.0 |
0.0 |
0.0 |
0.0 |
0.0 |
0.0 |
0.0 |
0.0 |
0.0 |
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The 2016 International RERTR Meeting (RERTR-2016) will take place in Belgium.
Stay tuned for further details.
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The 2015 International RERTR Meeting (RERTR-2015) took place in Seoul, Korea on Oct. 11-14, 2015.
For more information visit RERTR-2015.
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ANL/RERTR/TM-26 |
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Last modified on
July 29, 2008 11:33 +0200
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