New dynamic method to measure rod worths in zero power physics test at PWR startup

Annals of Nuclear Energy

Volumn 32, Issue 13, 2005, Pages 1457-1475

  Lee, E K ^a   Shin, H C ^a   Bae, S M ^a   Lee, Y K ^a  

^a Korea Electric Power Research Institute (KEPRI)   (South Korea)

Author keywords

[No Author keywords available]

Indexed keywords

COMBUSTION; COMPUTATION THEORY; NEUTRONS; NUCLEAR PHYSICS; NUCLEAR POWER PLANTS; PROBLEM SOLVING;

DYNAMIC CONTROL ROD REACTIVITY MEASUREMENT (DCRM); FLUX DISTRIBUTION; REACTIVITY CURVES; ZERO POWER PHYSICS;

PRESSURIZED WATER REACTORS;

EID: 22544473650     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.anucene.2005.04.008     Document Type: Article

References (14)

1. Chao, Y.A., et al., 1997. Dynamic rod worth measurement (DRWM) next generation rod worth measurement method. In: Proc. Topl. Mtg. Advances in Nuclear Fuel Management II, Myrtle Beach, South Carolina, USA, March 23-26, pp. 14-53, ANS.
2. Y.A. Chao Dynamic rod worth measurement Nucl. Tech. 132 2000 403
3. Kastanya, D.F., Ariani, I., Turinsky, P.J., 1997. Verification of dynamic rod worth measurement calculation methodology. In: Proc. Topl. Mtg. Advances in Nuclear Fuel Management II, Myrtle Beach, South Carolina, USA, March 23-26, pp. 14-65, ANS.
4. Lee, E.K., et al. 1999. A performance test of core-reflector boundary conditions on transient non-linear coarse mesh finite difference method based on the NEM," In: Proceedings of the KNS Autumn Meeting, October 29-30, Seoul, South Korea.
5. Lee, E.K., 2002. Incorporation & Application of DRMRW to Three-loop Westinghouse & C-E system 80+ NSSSs Using KEPRI Nuclear Design Codes. TM.00NJ02.P2002.355, KEPRI.
6. Lee, E.K., et al. 2002. A performance test of non-linear NEM/ANM CMFD in LWR core Transient, In: Proceedings of the KNS-KARP Joint spring meeting, May 23-24, Gwangju, South Korea.
7. Lee, E.K., et al. 2004. Application of the dynamic control rod reactivity measurement method to Korea Standard Nuclear Power Plants. In: Proceedings of the PHYSOR 2004, Chicago, IL, April 25-29, ANS.
8. W.A. Rhoades, and R.L. Childs The DORT two-dimensional discrete ordinates transport code Nucl. Sci. Eng. 99 1988 1
9. Liu, Y.S., et al. 1986. ANC A Westinghouse Advanced Nodal Computer Code. WCAP-11596-P-A.
10. Loretz, R., et al. 1996. The ROCS and DIT Computer Codes for Nuclear Design. CE-CES-4 Rev. Combustion Engineering Inc.
11. Finnemman, H., et. al. 1993. Results of LWR Core Transient Benchmark. NEA/NSC/DOC(93)25.
12. Fraikin, R., et al. 1997. PWR Benchmark on Uncontrolled Withdrawal of Control Rods at Zero Power. NEA/NSC/DOC(96)20.
13. Ivanov, K.N., et al. 1999. PWR Main Steam Line Break (MSLB) Benchmark. NEA/NSC/DOC(99)8.
14. Shober, R.A., 1978. A Nodal Method for Solving Transient Few Group Neutron Diffusion Equation. ANL-78-51. Argonne National Lab.