Design study of small Pressurized Water Reactors (PWRs) core loaded with uranium nitride fuel (UN) and mixed nitride fuel (UN-PuN), Pa-231 as burnable poison, and Americium has been performed. Pa-231 known as actinide material, have large capture cross section and can be converted into fissile material that can be utilized to reduce excess reactivity. Americium is one of minor actinides with long half life. The objective of adding americium is to decrease nuclear spent fuel in the world. The neutronic analysis results show that mixed nitride fuel have k-inf greater than uranium nitride fuel. It is caused by the addition of Pu-239 in mixed nitride fuel. In fuel fraction analysis, for uranium nitride fuel, the optimum volume fractions are 45% fuel fraction, 10% cladding and 45% moderator. In case of UN-PuN fuel, the optimum volume fractions are 30% fuel fraction, 10% cladding and 60% coolant/ moderator. The addition of Pa-231 as burnable poison for UN fuel, enrichment U-235 5%, with Pa-231 1.6% has k-inf more than one and excess reactivity of 14.45%. And for mixed nitride fuel, the lowest value of reactivity swing is when enrichment (U-235+Pu) 8% with Pa-231 0.4%, the excess reactivity value 13,76%. The fuel pin analyze for the addition of Americium, the excess reactivity value is lower than before, because Americium absorb the neutron. For UN fuel, enrichment U-235 8%, Pa-231 1.6% and Am 0.5%, the excess reactivity is 4.86%. And for mixed nitride fuel, when enrichment (U-235+Pu) 13%, Pa-231 0.4% and Am 0.1%, the excess reactivity is 11.94%. For core configuration, it is better to use heterogeneous than homogeneous core configuration, because the radial power distribution is better.
Skip Nav Destination
,
Article navigation
30 September 2015
THE 5TH INTERNATIONAL CONFERENCE ON MATHEMATICS AND NATURAL SCIENCES
2–3 November 2014
Bandung, Indonesia
Research Article|
September 30 2015
The prospect of uranium nitride (UN) and mixed nitride fuel (UN-PuN) for pressurized water reactor
Ratna Dewi Syarifah;
Ratna Dewi Syarifah
a)
1Nuclear Physics and Biophysics Research Division, Physics Department, Faculty of Mathematics and Natural Science,
Bandung Institute of Technology
Jalan Ganesha 10, Bandung 40132, Indonesia
Search for other works by this author on:
Ratna Dewi Syarifah
1,a)
Zaki Suud
1,b)
1Nuclear Physics and Biophysics Research Division, Physics Department, Faculty of Mathematics and Natural Science,
Bandung Institute of Technology
Jalan Ganesha 10, Bandung 40132, Indonesia
AIP Conf. Proc. 1677, 120005 (2015)
Citation
Ratna Dewi Syarifah, Zaki Suud; The prospect of uranium nitride (UN) and mixed nitride fuel (UN-PuN) for pressurized water reactor. AIP Conf. Proc. 30 September 2015; 1677 (1): 120005. https://doi.org/10.1063/1.4930788
Download citation file:
Pay-Per-View Access
$40.00
Sign In
You could not be signed in. Please check your credentials and make sure you have an active account and try again.
Citing articles via
The implementation of reflective assessment using Gibbs’ reflective cycle in assessing students’ writing skill
Lala Nurlatifah, Pupung Purnawarman, et al.
Inkjet- and flextrail-printing of silicon polymer-based inks for local passivating contacts
Zohreh Kiaee, Andreas Lösel, et al.
Effect of coupling agent type on the self-cleaning and anti-reflective behaviour of advance nanocoating for PV panels application
Taha Tareq Mohammed, Hadia Kadhim Judran, et al.
Related Content
Design study of Thorium-232 and Protactinium-231 based fuel for long life BWR
AIP Conf. Proc. (June 2012)
Neutronic investigation of integral burnable absorber (UO2-Gd2O3) different pattern arrangement on nuscale reactor fuel assembly
AIP Conf. Proc. (February 2024)
The effect of new library cross-section on fuel using gadolinium burnable poison
AIP Conf. Proc. (February 2024)
An americium‐fueled gas core nuclear rocket
AIP Conf. Proc. (January 1993)
Optimization of small long-life PWR based on thorium fuel
AIP Conf. Proc. (September 2015)