Published December 2011 | Version v1
Miscellaneous Open

Criticality evaluation of PWR1000 core at optimized power reactor type

  • 1. Center for Reactor Technology and Nuclear Safety, National Nuclear Energy Agency, Kawasan Puspiptek Gd 80, Serpong, Tangerang Selatan 15314 (Indonesia)

Description

Criticality evaluation of the PWR1000 core at optimized power reactor been done using (Monte Carlo N-Particle) MCNP4C computer code. The aim of calculation is to know the characteristic one of the cores of PWR1000 MWe namely OPR1000 core. The OPR1000 reactor is one of PWR types NPP with passive safety condition. One of the important parameter to understand the design characteristic is a core criticality. Evaluation of the design calculation was done for the OPR core which used solid fuels UO2 with power thermal 2825 MWt. The enrichment fuel compositions were 1.60 %, 3.28 % and 2,78 % with gadolinia as a burnable poison. The OPR core used 16x16 grids of fuel assemblies with 236 pin rods, 4 guide tubes and 1 instrument tube. The OPR reactor has 177 fuel assemblies in the core in matrix of 15x15. MCNP4C code is one of the core calculation code used Monte Carlo method which has good validation. The result of calculation showed that the value of keff for OPR1000 core is 1,17912 it is lower than other keff value of PWR cores. So the core of OPR1000 reactor is a low boron concentration that means the reactor need low boron concentration become the core subcritical condition. (author)

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Part of:
Proceedings of the 17th National Seminar on Technology and Safety for Nuclear Power Plants and Nuclear Facilities

Additional details

Additional titles

Original title (Indonesian)
Evaluasi kritikalitas teras PWR1000 MWe jenis optimazed power reactor

Publishing Information

Publisher
Center for Reactor Technology and Nuclear Safety, National Nuclear Energy Agency
Imprint Place
Tangerang Selatan (Indonesia)
Imprint Title
Proceedings of the 17"t"h National Seminar on Technology and Safety for Nuclear Power Plants and Nuclear Facilities
Imprint Pagination
724 p.
Journal Page Range
p. 300-309
ISSN
0854-2910
Report number
INIS-ID--113

Conference

Title
17. National Seminar on Technology and Safety of Nuclear Power Plants and Nuclear Facilities
Original Conference Title
Seminar Nasional ke-17 Teknologi dan Keselamatan PLTN Serta Fasilitas Nuklir
Dates
1 Oct 2011
Place
Yogyakarta (Indonesia)

Optional Information

Notes
7 refs.; 5 tabs.; 5 figs. Imprint:Prosiding Seminar Nasional ke-17 Teknologi dan Keselamatan PLTN Serta Fasilitas Nuklir