Parametric Study of Time-Dependent Corrosion Product Activity due to56Mn,58Co, and60Co in the Primary Coolant Circuit of a Typical Pressurized Water Reactor

Muhammad Rafique,Sikander M Mirza,Syed F Naeem,Nasir M Mirza,Shahab A Abbasi,Kimberlee J Kearfott

doi:10.1155/2015/809672

Abstract

Results of a detailed study, based on the parametric analysis of activated corrosion products, in primary coolant of a typical pressurized water reactor (PWR) are presented. The parameters influencing time dependent buildup of corrosion product activity (CPA) in primary coolant loop of PWR were identified. The computer program CPAIR was used to accommodate for time dependent corrosion rates. The behaviors of56Mn,58Co, and60Co were studied over the reactor operational time. During the course of normal operation of reactor, the CPA is dominated by56Mn, while58Co and60Co are the predominant radionuclides after reactor shutdown. Parametric study suggests that the total CPA is most sensitive to ion-exchanger removal rates. For a removal rate of 300 cm3-s−1, the specific activity due to56Mn has the maximum value of 3.552 × 104 Bq-m−3after 1,000 hours of reactor operation. This value decreases drastically to 8.325 × 103 Bq-m−3at removal rate of 900 cm3-s−1. Additionally, CPA due to56Mn,58Co, and60Co shows strong dependence on removal rates from the core material surfaces. Variations in the values of radionuclide removal rates from piping surface and radionuclide removal rate from deposition on pipes showed only very small effects on CPA buildup.

Highlights

Corrosion products activated by high neutron flux in the reactor core are the dominant contributors to the postshutdown radiation field (PSRF) for all water reactors
Specific activity in primary coolant of pressurized water reactor (PWR) decreases with increasing removal rates
Corrosion products are strong contributors to radiation levels produced in personnel working environment of PWR, and the estimation of corrosion product activity (CPA) is important

Summary

Introduction

Corrosion products activated by high neutron flux in the reactor core are the dominant contributors to the postshutdown radiation field (PSRF) for all water reactors. Pressurized water reactors (PWRs) have an order of magnitude higher PSRF values compared to gas-cooled reactors. Several authors [2,3,4,5,6,7,8,9,10,11,12,13,14,15,16,17,18] carried out investigations on the formation, transport, and deposition of radioactive corrosion products in various parts of PWRs. Several models were developed to simulate corrosion product transport and the buildup of activity in the primary coolant systems of PWRs. The PACTOLE program [4] was developed for predicting the time-dependent behavior of the activation of PWR corrosion products. The DISER program [21] simulates corrosion product activity (CPA), assuming that the coolant contains

Methods

Results

Conclusion