Abstract

In order to increase the storage capacity of the East Spent Fuel Pool at the Cofrentes NPP, located in Valencia province, Spain, the existing storage stainless steel racks were replaced by a new design of compact borated stainless steel racks allowing a 65% increase in fuel storing capacity. Calculation of the activation of the used racks was successfully performed with the use of MCNP4B code. Additionally the dose rate at contact with a row of racks in standing position and behind a wall of shielding material has been calculated using MCNP4B code as well. These results allowed a preliminary definition of the burnker required for the storage of racks. Recently the activity in the racks has been recalculated with SEACAB system which combines the mesh tally of MCNP codes with the activation code ACAB, applying the rigorous two-step method (R2S) developed at home, benchmarked with FNG irradiation experiments and usually applied in fusion calculations for ITER project.

Highlights

  • The reracking of a spent fuel pool is a frequent need in the effort to increase wet storage capacity of nuclear power plants

  • Cofrentes NPP, is a General Electric BWR-6 Mark III located in Valencia province, Spain, having two different wet storage ponds

  • In order to increase the storage capacity of the East Fuel Storage Pond (PACE in Spanish) the existing stainless steel racks were replaced by a new design of compact borated stainless steel racks allowing a 65% increase in fuel storing capacity

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Summary

Introduction

The reracking of a spent fuel pool is a frequent need in the effort to increase wet storage capacity of nuclear power plants. Cofrentes NPP, is a General Electric BWR-6 Mark III located in Valencia province, Spain, having two different wet storage ponds. At the removal of the old racks a decontamination process was performed eliminating completely the removable contamination but the intrinsic activity due to neutron irradiation needed to be estimated for designing the shielding of its interim storage at the plant. The neutron source was calculated with the use of the traditional SAS2H sequence inside the 4.4 version of SCALE [2]. The final purpose of the activation calculation is the determination of the total Co60 photon source in the used racks to allow the design of a specific bunker inside the Almacén de Piezas de Baja Actividad o APBA (Low Activity Pieces Store), located at Cofrentes site.

CALCULATION PROCESS
Estimation of fuel assembly burnup
Activation of the rack channel
Activation calculations with MCNP4B
Recalculations with SEACAB
Dose calculations
Findings
Summary and conclusions

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