ANALYSIS OF PLUTONIUM COMPOSITION NON-PROLIFERATION ASPECT ON NUCLEAR POWER PLANT
Research about plutonium composition non proliferation aspect on many types nuclear power plant has been done on this final project. Analysis that has been done is about the production of isotopes of plutonium, uranium and minor actinides such as neptunium, americium, and curium. In addition, neutro...
Saved in:
| Main Author: | |
|---|---|
| Format: | Final Project |
| Language: | Indonesia |
| Online Access: | https://digilib.itb.ac.id/gdl/view/23266 |
| Tags: |
Add Tag
No Tags, Be the first to tag this record!
|
| Institution: | Institut Teknologi Bandung |
| Language: | Indonesia |
| Summary: | Research about plutonium composition non proliferation aspect on many types nuclear power plant has been done on this final project. Analysis that has been done is about the production of isotopes of plutonium, uranium and minor actinides such as neptunium, americium, and curium. In addition, neutronic characteristics such reactor neutron multiplication factor and conversion ratio were also analyzed. The reactor used for this study is a pressurized water reactor (PWR), Boiling water reactor (BWR), CANDU reactor (Canada Deuterium-Uranium) and High Temperature Gas-cooled reactor (HTGR). SRAC program with PIJ module are used to carry out a burnup simulation. Other than that, ORIGEN program is also used to carry out a simulation of burnup and cooling process for several types of reactor. <br />
<br />
<br />
parameter that used in simulation are a standard reactor with enrichment that‟s different for each type of reactor. enrichment of uranium-235 in PWR and BWR used were as much as 3%, for HTGR is 6% and 1,25% in CANDU reactors. burnup <br />
<br />
<br />
target values used in SRAC program is equated to all the reactors which is 33 GWd/t while the burnup used in ORIGEN are disparate. Data obtained from the simulation with PIJ module are neutron multiplication factor, conversion rate, and the composition of actinides. To analyze the non-proliferation aspects of the reactor, the value of Decay heat (DH) and Spontaneous Fission Neutron (SFN) based on <br />
<br />
<br />
Plutonium composition are calculated. From simulation using ORIGEN, value of DH and SFN obtained at the end of the cycle after 50 years of cooling process for PWR, BWR, and LMFBR and CANDU reactor respectively were 10.5, 8.9, 7.3, 5.7 W/kg dan 3.81E+5, 3.67E+5, 3.99E+5, 4.83E+5 n/s/kg. from the calculation using the ORIGEN with different reactor parameters from SRAC, it was found that the value <br />
<br />
<br />
of DH when cooling process are decreasing while value of SFN continues to increase. Based on non-proliferation factor of decay heat from plutonium, PWR had <br />
<br />
<br />
the highest value. Based on spontaneous fission neutron, CANDU reactor got the highest value. The non-proliferation value get better along with the increasing <br />
<br />
<br />
composition of even mass plutonium |
|---|