Table B1. TRIGA Fuel 25-Rod Cluster Model [ANL/RERTR/TM-26 Report]

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Table B1. TRIGA Fuel 25-Rod Cluster Model


TRIGA Fuel	10wt% U, 93.1% Enrichment				41.4	g U-235		TRIGA Fuel	45wt% U, 19.7% Enrichment				53.6	g U-235

U-235 Burnup, %	0	10	20	30	40	50	60	U-235 Burnup, %	0	10	20	30	40	50	60
U-235 Burned, g	0.0	4.1	8.3	12.4	16.6	20.7	24.8	U-235 Burned, g	0.0	5.4	10.7	16.1	21.4	26.8	32.2
U-234	0.4	0.4	0.4	0.4	0.4	0.3	0.3	U-234	0.4	0.4	0.4	0.3	0.3	0.3	0.3
U-235	41.4	37.2	33.1	29.0	24.8	20.7	16.6	U-235	53.6	48.3	42.9	37.5	32.2	26.8	21.4
U-236	0.2	1.0	1.7	2.4	3.1	3.8	4.4	U-236	0.7	1.7	2.7	3.7	4.6	5.5	6.4
U-238	2.4	2.4	2.4	2.3	2.3	2.2	2.2	U-238	217.4	216.5	215.6	214.6	213.5	212.3	210.9
U	44.5	41.0	37.6	34.1	30.6	27.1	23.5	U	272.1	266.9	261.6	256.1	250.6	244.9	239.0
Np-237	0	0.0	0.0	0.1	0.1	0.2	0.2	Np-237	0	0.0	0.1	0.1	0.2	0.3	0.4
Np	0	0.0	0.0	0.1	0.1	0.2	0.2	Np	0	0.0	0.1	0.1	0.2	0.3	0.4
Pu-238	0	0.0	0.0	0.0	0.0	0.0	0.0	Pu-238	0	0.0	0.0	0.0	0.0	0.1	0.1
Pu-239	0	0.0	0.1	0.1	0.1	0.1	0.1	Pu-239	0	0.7	1.3	1.7	1.9	2.1	2.1
Pu-240	0	0.0	0.0	0.0	0.0	0.0	0.0	Pu-240	0	0.0	0.1	0.2	0.3	0.4	0.5
Pu-241	0	0.0	0.0	0.0	0.0	0.0	0.0	Pu-241	0	0.0	0.0	0.1	0.2	0.3	0.4
Pu-242	0	0.0	0.0	0.0	0.0	0.0	0.0	Pu-242	0	0.0	0.0	0.0	0.0	0.1	0.1
Pu	0	0.0	0.1	0.1	0.1	0.1	0.2	Pu	0	0.8	1.4	2.0	2.5	2.9	3.2
Am-241	0	0.0	0.0	0.0	0.0	0.0	0.0	Am-241	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	Am	0	0.0	0.0	0.0	0.0	0.0	0.0

TRIGA Fuel	10wt% U, 93.1% Enrichment				41.4	g U-235		TRIGA Fuel	45wt% U, 19.7% Enrichment				53.6	g U-235

U-235 Burnup, %	0	10	20	30	40	50	60	U-235 Burnup, %	0	10	20	30	40	50	60
U-235 Burned, g	0.0	4.1	8.3	12.4	16.6	20.7	24.8	U-235 Burned, g	0.0	5.4	10.7	16.1	21.4	26.8	32.2
U-234	0.0	0.0	0.0	0.0	0.0	0.0	0.0	U-234	0.0	0.0	0.0	0.0	0.0	0.0	0.0
U-235	41.4	37.2	33.1	29.0	24.8	20.7	16.6	U-235	53.6	48.3	42.9	37.5	32.2	26.8	21.4
U-236	0.0	0.8	1.5	2.3	2.9	3.6	4.2	U-236	0.0	1.1	2.1	3.1	4.0	4.9	5.7
U-238	2.4	2.4	2.4	2.3	2.3	2.2	2.2	U-238	217.4	216.5	215.6	214.6	213.5	212.3	211.0
U	43.8	40.4	37.0	33.5	30.1	26.5	23.0	U	271.1	265.9	260.6	255.2	249.7	244.0	238.1
Np-237	0	0.0	0.0	0.1	0.1	0.1	0.2	Np-237	0	0.0	0.0	0.1	0.2	0.2	0.3
Np	0	0.0	0.0	0.1	0.1	0.1	0.2	Np	0	0.0	0.0	0.1	0.2	0.2	0.3
Pu-238	0	0.0	0.0	0.0	0.0	0.0	0.0	Pu-238	0	0.0	0.0	0.0	0.0	0.0	0.1
Pu-239	0	0.0	0.1	0.1	0.1	0.1	0.1	Pu-239	0	0.7	1.3	1.7	1.9	2.1	2.1
Pu-240	0	0.0	0.0	0.0	0.0	0.0	0.0	Pu-240	0	0.0	0.1	0.2	0.3	0.4	0.5
Pu-241	0	0.0	0.0	0.0	0.0	0.0	0.0	Pu-241	0	0.0	0.0	0.1	0.2	0.3	0.4
Pu-242	0	0.0	0.0	0.0	0.0	0.0	0.0	Pu-242	0	0.0	0.0	0.0	0.0	0.1	0.1
Pu	0	0.0	0.1	0.1	0.1	0.1	0.2	Pu	0	0.8	1.4	2.0	2.5	2.9	3.2
Am-241	0	0.0	0.0	0.0	0.0	0.0	0.0	Am-241	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	Am	0	0.0	0.0	0.0	0.0	0.0	0.0

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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.

ANL/RERTR/TM-26

Introduction
Nuclear Mass Inventory
Photon Dose Rate
Thermal Decay Heat
Conclusions
References
Appendix A: MTR Model Mass Inventory Sensitivity
Appendix B: U-234 And U-236 Mass Inventory Sensitivity
Appendix C: Mass Inventory Estimate: ORIGEN Vs. WIMS
Appendix D: Example Calculation: Nuclear Mass Inventory, Photon Dose Rate And Thermal Decay Heat
PDF Version
the full paper in PDF format


	ARGONNE NATIONAL LABORATORY, Nuclear Engineering Division, RERTR Department 9700 South Cass Ave., Argonne, IL 60439-4814 A U.S. Department of Energy laboratory managed by UChicago Argonne, LLC

Last modified on July 29, 2008 11:34 +0200

RERTR Publications: Foreign Research Reactor Spent Nuclear Fuel

ANL/RERTR/TM-26

Table B1. TRIGA Fuel 25-Rod Cluster Model

RERTR Publications:
Foreign Research Reactor Spent Nuclear Fuel