Fuel Fabrication Process

<?xml version="1.0" encoding="UTF-8"?>
<holdings>
	<snri>
		<facility>RESEARCH REACTOR</facility>
		<location>REACTOR</location>
		<material-form>UO2 HEU FUEL assemblies</material-form>
		<assemblies>240 IN REACTOR</assemblies>
		<material-amount>686.4 KG U (36%)</material-amount>
		<total-isotopes>247.2 KG U235</total-isotopes>
		<radiation-levels>HIGH - Greater than 1 sV/h @1M</radiation-levels>
	</snri>
	<snri>
		<facility>RESEARCH REACTOR</facility>
		<location>R090 FRESH FUEL VAULT</location>
		<material-form>UO2 HEU FUEL assemblies</material-form>
		<assemblies>80 IN STORAGE</assemblies>
		<material-amount>228.9 KG U (36%)</material-amount>
		<total-isotopes>82.4 KG U235</total-isotopes>
		<radiation-levels>LOW</radiation-levels>
	</snri>
	<snri>
		<facility>RESEARCH REACTOR</facility>
		<location>IRRADIATED FUEL POOL</location>
		<material-form>UO2 HEU FUEL assemblies</material-form>
		<assemblies>100 IN POOL</assemblies>
		<material-amount>28.6 KG U (36%)</material-amount>
		<total-isotopes>10.3 KG U235</total-isotopes>
		<radiation-levels>HIGH - less than 0.2 sV/h @1M</radiation-levels>
	</snri>
	<snri>
		<facility>RESEARCH REACTOR</facility>
		<location>R091 PRODUCT VAULT</location>
		<material-form>HEU METAL</material-form>
		<assemblies>N/A</assemblies>
		<material-amount>23 KG U (95%)</material-amount>
		<total-isotopes>22 KG U235</total-isotopes>
		<radiation-levels>LOW</radiation-levels>
	</snri>	
	<snri>
		<facility>WASTE STORAGE</facility>
		<location>TANKS</location>
		<material-form>LIQUID MIXTURE - 2 TANKS 1,000L PER</material-form>
		<assemblies>N/A</assemblies>
		<material-amount>~1 G U (3%)</material-amount>
		<total-isotopes>~1 G U235</total-isotopes>
		<radiation-levels>HIGH - 1 Sv/h @ 1m</radiation-levels>
	</snri>	
	<snri>
		<facility>WASTE STORAGE</facility>
		<location>SMALL BUILDINGS</location>
		<material-form>SOLIDIFIED WASTE - 50 CONTAINERS</material-form>
		<assemblies>N/A</assemblies>
		<material-amount>TRACE AMOUNTS U (4-10%)</material-amount>
		<total-isotopes>TRACE AMOUNTS U235</total-isotopes>
		<radiation-levels>HIGH - less than .5SV/h @1M</radiation-levels>
	</snri>	
	<snri>
		<facility>X-RAY</facility>
		<location>MAIN ROOM</location>
		<material-form>FUEL PINS And METAL</material-form>
		<assemblies>NOT PLACED INTO assemblies</assemblies>
		<material-amount>8.6KG U (36%) and 5.2KG u (95%)</material-amount>
		<total-isotopes>3.1 KG U235 and 5 KG U235</total-isotopes>
		<radiation-levels>LOW and LOW</radiation-levels>
	</snri>	
	<snri>
		<facility>WASTE MEASUREMENT</facility>
		<location>MAIN ROOM</location>
		<material-form>WASTE DRUMS</material-form>
		<assemblies>N/A</assemblies>
		<material-amount>1KG U</material-amount>
		<total-isotopes>TRACE</total-isotopes>
		<radiation-levels>LOW</radiation-levels>
	</snri>	
	<snri>
		<facility>OXIDE STORAGE BUNKER</facility>
		<location>BUNKER</location>
		<material-form>UOS HEU (POWDER)</material-form>
		<assemblies>SMALL CONTAINERS</assemblies>
		<material-amount>250 KG U (36%)</material-amount>
		<total-isotopes>90 KG U235</total-isotopes>
		<radiation-levels>LOW</radiation-levels>
	</snri>	
	<snri>
		<facility>FUEL FABRICATION BUILDING</facility>
		<location>OXIDE VAULT</location>
		<material-form>UO2 HEU (POWDER)</material-form>
		<assemblies>CONTAINERS</assemblies>
		<material-amount>94.5KG U (36%)</material-amount>
		<total-isotopes>34 KG U235</total-isotopes>
		<radiation-levels>LOW</radiation-levels>
	</snri>	
	<snri>
		<facility>FUEL FABRICATION BUILDING</facility>
		<location>PIN VAULT</location>
		<material-form>UO2 HEU (PELLETS IN PINS)</material-form>
		<assemblies>SEALED PINS</assemblies>
		<material-amount>69.5KG U (36%)</material-amount>
		<total-isotopes>25 KG U235</total-isotopes>
		<radiation-levels>LOW</radiation-levels>
	</snri>	
	<snri>
		<facility>FUEL FABRICATION BUILDING</facility>
		<location>PELLET VAULT</location>
		<material-form>UO2 HEU (PELLETS)</material-form>
		<assemblies>CONTAINERS</assemblies>
		<material-amount>69.5KG U (36%)</material-amount>
		<total-isotopes>25 KG U235</total-isotopes>
		<radiation-levels>LOW</radiation-levels>
	</snri>	
	<snri>
		<facility>ANALYTICAL LABORATORY</facility>
		<location>LAB</location>
		<material-form>SAMPLES ALL FORMS</material-form>
		<assemblies>SAMPLES ALL FORMS</assemblies>
		<material-amount>1.1KG U (36%)</material-amount>
		<total-isotopes>400 G U235</total-isotopes>
		<radiation-levels>LOW</radiation-levels>
	</snri>	
	<snri>
		<facility>SHIPPING and RECEIVING</facility>
		<location>HIGH BAY</location>
		<material-form>OXIDES and HOT WASTE</material-form>
		<assemblies>CONTAINERS</assemblies>
		<material-amount>NOT APPROVED FOR OVER NIGHT STORAGE</material-amount>
		<total-isotopes>N/A</total-isotopes>
		<radiation-levels>LOW</radiation-levels>
	</snri>	
</holdings>

Fuel Fabrication

The annual throughput of the SNRI is approximately 1 metric ton of uranium of various enrichments. When a fuel batch is needed and none are available at the desired enrichment, a quantity of UO2 is collectedand batched according to the enrichment requirements.

Click here to find out more about SNRI's fuel fabrication processes.

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About SNRI

SNRI was established in 1950 to serve as the primary nuclear energy research facility for the Republic of Anshar. The instititue houses various research, fuel fabrication, administrative, and plant support facilities.

The institute is located approximately 29km from Utu; Anshar's beautiful capital city.

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Fuel Fabrication

About SNRI

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