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Burnable poison
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This work presents the neutronic analysis of fuel design for a long-life core in a pressurized water reactor (PWR). In order to achieve a high burnup, a high enrichment U235 is traditionally considered without special constraints against proliferation. To counter the excess reactivity, Erbium was selected as a burnable poison due to its good depletion performance.
7p
vicedric
08-02-2023
7
3
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Application of Gd2O3 in form of burnable poison particles (BPPs) has been investigated for improving neutronics performance of VVER-1000 fuel assembly. Numerical calculations have been conducted for optimizing BPP parameters using the MVP code and the JENDL-3.3 data library.
7p
visnape
30-01-2023
9
4
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This paper presents the neutronic feasibility study on transmutation of minor actinide as burnable poison in the VVER-1000 LEU (low enriched uranium) fuel assembly. The VVER-1000 LEU fuel assembly was modeled using the SRAC code system.
10p
visnape
30-01-2023
8
5
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The VVER-1000 reactors are nowadays widespread used in Russia and numerous countries. With almost 3000 MW of thermal, VVER-1000 is a candidate to transmute minor actinides (MAs) which are the main contributors to the radiotoxicity and decay heat of nuclear spent fuel (SNF).
11p
visnape
30-01-2023
8
4
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The comparative analysis was conducted for the two models of minor actinide loading in the LEU fuel assembly: homogeneous mixing in the UGD (Uranium-Gadolinium) pins and coating a thin layer to the UGD pins. The parameters to be analysed and compared include the reactivity of the LEU fuel assembly versus burnup and the transmutation of minor actinide nuclides when loading different minor actinide vectors into the LEU fuel assembly.
11p
trinhthamhodang1218
14-03-2021
6
3
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Thermale - hydraulic characteristics for canflex fuel channel using burnable poison in candu reactor
The thermalehydraulic characteristics for the CANadian Deuterium Uranium Flexible (CANFLEX)-burnable poison (BP) fuel channel, which is loaded with a BP at the center ring based on the CANFLEX-RU (recycled uranium) fuel channel, are evaluated and compared with that of standard 37-element and CANFLEX-NU (natural uranium) fuel channels. The distributions of fuel temperature and critical channel power for the CANFLEX-BP fuel channel are calculated using the NUclear Heat Transport.
8p
minhxaminhyeu5
30-06-2019
14
0
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The aim of this book is to disseminate state-of-the-art research and advances in the area of nuclear reactors technology. The book was divided in two parts.
0p
phoebe75
19-02-2013
65
8
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