Design Study of Pb-Bi Cooled Fast Reactor with Natural Uranium Fuel Base Using Shuffling Strategy
Design study of Lead-bismuth cooled fast reactor with natural uranium fuel base has been done. The reactors utilize UN-PUN as fuel and timbale-bismuth as coolant and can be operated without refueling for 10 years with initial excess reactivity 9%. Calculation has been done by using SRAC system code...
Saved in:
| Main Author: | |
|---|---|
| Format: | Theses |
| Language: | Indonesia |
| Online Access: | https://digilib.itb.ac.id/gdl/view/11271 |
| Tags: |
Add Tag
No Tags, Be the first to tag this record!
|
| Institution: | Institut Teknologi Bandung |
| Language: | Indonesia |
| Summary: | Design study of Lead-bismuth cooled fast reactor with natural uranium fuel base has been done. The reactors utilize UN-PUN as fuel and timbale-bismuth as coolant and can be operated without refueling for 10 years with initial excess reactivity 9%. Calculation has been done by using SRAC system code and JENDL-32 library, with cylindrical cell two dimensional R-Z core models. Reactor design optimization is evaluated to utilize natural uranium as reactor fuel. Optimization evaluated by burning natural uranium for 60 years and put each of its burn up result per year in reactor with certain configuration. The placement of fuel in core arranged so that the result of natural uranium burnt sufficient for 10 years reactor operation in 6 core region. The 1st year to 10th year of burn up result placed at region 6, the 11th year to 20th year of burn up result placed at region 1, the 21st year to 30th year of burn up result placed at region 2, and so on so that the 51st year to 60th year of burn up result place at region 5. This natural uranium initially being burned by guessed power level of burn up. After CITATION calculation, new power level will be obtained to be used for the next cell calculation. The process is repeated until the power level value is convergent. To maintain the reactor for 10 years operation, fuel-to-coolant ratio survey has been done. With height and diameter core 250 cm and 200 cm respectively, the appropriate volume fraction for this design is 61% fuel, 10% cladding and 29% coolant. <br />
|
|---|