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Nuclear and thermal hydraulic calculation of a representative I2S-LWR first core

Radomir Ječmenica ; University of Zagreb Faculty of Electrical Engineering and Computing Unska 3, 10000 Zagreb, Croatia
Davor Grgić ; University of Zagreb Faculty of Electrical Engineering and Computing Unska 3, 10000 Zagreb, Croatia
Mario Matijević ; University of Zagreb Faculty of Electrical Engineering and Computing Unska 3, 10000 Zagreb, Croatia
Bojan Petrović ; Georgia Institute of Technology, Nuclear and Radiological Engineering 770 State St., Atlanta, GA 30332-0745, USA

Sažetak

The Integral Inherently Safe Light Water Reactor (I2S-LWR) concept developed by Georgia
Tech is a novel PWR reactor delivering electric power of 1000 MWe while implementing inherent
safety features typical for Generation III+ small modular reactors. The main safety feature is based
on integral primary circuit configuration, bringing together compact design of the reactor core (121
fuel assembly), control rod drive mechanism (CRDM), 8 primary heat exchangers (PHE), 4 passive
decay heat removal systems (DHRS), 8 pumps, and other integral components. A high power
density core based on silicide fuel and APMT (FeCrAl) stainless steel cladding is selected to
achieve a high thermal power. Initial representative first core nuclear design is proposed by
Westinghouse. Full core 3D depletion calculation was performed using PARCS code. The cross
section library is prepared using FA2D code and verified using Polaris sequence from SCALE 6.2
beta5. The axial and radial reflectors are assumed to be homogeneous water-APMT mixtures. The
axial reflectors are both assumed to be 12 inch (30.48 cm) sections composed of 30% APMT steel
by volume. The radial reflector is assumed to be 90% APMT steel by volume. The reflector
constants were calculated using SCALE TRITON sequence. The thermal hydraulic part of the
model is based on COBRA subchannel code coupled to PARCS code. Initial depletion calculation
is based on one thermal hydraulics channel per fuel assembly approach. The hot fuel assembly is
determined using separate pin-by-pin COBRA subchannel model and pin power reconstruction data
from PARCS. The objective of the paper is demonstration of LWR design methodology
applicability to silicide fuel and identification of possible improvements in the first core design.

Ključne riječi

I2S-LWR; core design; PARCS; COBRA; SCALE; FA2D

Hrčak ID:

199635

URI

https://hrcak.srce.hr/199635

Datum izdavanja:

15.10.2017.

Posjeta: 474 *