Elsevier

Nuclear Engineering and Design

Volume 277, 1 October 2014, Pages 248-264
Nuclear Engineering and Design

A proposed aging management program for alkali silica reactions in a nuclear power plant

https://doi.org/10.1016/j.nucengdes.2014.06.012Get rights and content

Abstract

Drawing from publicly available information, this paper addresses the alkali silica reaction management of Seabrook nuclear power plant.

The essence of the reaction is first examined, followed by a summary of findings, current and planned work. Then, the authors draw on their experience in ASR to first comment on the current work, and then complete the paper with what they would recommend.

An important observation is that ASR constitutes a major challenge to the nuclear industry, and a thorough understanding of the State of the Art is essential before a holistic approach is undertaken. It is neither a simple nor an inexpensive challenge, yet a most critical one that industry and regulators must confront. This paper is only a breach into such an effort.

Introduction

It is a matter of public record that Seabrook nuclear power plant (NPP) appears to be suffering from alkali silica reaction (ASR) in a localized zone of its subbasement. Drawing exclusively from publicly available information from the Agency wide Document Access and Management System (ADAMS), the authors provide an unsolicited personal and independent opinion on the management of this problem based primarily on the senior author's experience with ASR (Saouma and Perotti, 2006, Saouma et al., 2007, Saouma et al., 2014, Puatatsananon and Saouma, 2013, Saouma, 2013).

First ASR will be briefly explained, then the presence of ASR in nuclear power plants will be discussed, followed by the role of irradiation on ASR. Issues pertaining to the life-extension of NPP will be discussed in general, followed by a factual presentation of the role of ASR in Seabrook NPP (as published in ADMAS). The paper will conclude with the authors personal comments on some of the actions presently taken, and finally what they would personally recommend.

Section snippets

What is ASR

ASR was first identified by Stanton (1940) as a cause for concrete deterioration and is likely the leading cause of dam concrete deterioration. This slowly evolving internal concrete damage causes millions of dollars in damage worldwide, given that no (economically) feasible method is available to stop the reaction. More recently, there has been evidence of ASR in nuclear power plants (see below).

Alkali–silica reaction is an acid–base one. The acid reactant is silica in the solid state, the

ASR in nuclear power plants

Despite the lack of publicity, some nuclear power plants reactors are starting to show signs of ASR.

In Japan, the (reinforced concrete) turbine generator foundation at Ikata No. 1 NPP (owned by Shihoku Electric Power) exhibits ASR expansion and has thus been the subject of many studies. Takatura et al. (2005a) reports on the field investigation work underway: location, extent of cracking, variation in concrete elastic modulus and compressive strength, expansion in sufficient detail to

Role of irradiation on ASR

It has long been known that irradiation affects concrete properties; the classical work by Hilsdorf et al. (1978) remains pertinent today given the complexity of conducting supportive experiments.

The possibility that nuclear irradiation can significantly increase the reactivity of silica-rich aggregates (hence the potential for ASR) was first raised by Ichikawa and Koizumi (2002). Let's begin by the author's summary of the state of knowledge in 2002:

  • Gamma rays do not affect concrete properties

Life extension

According to the Atomic Energy Act of 1954 (NUREG-0980, 2013), and Nuclear Regulatory Commission (NRC) regulations, the operating licenses for commercial power reactors are issued for 40 years and can be renewed for an additional 20 years, with no limit to the number of renewals. The original 40-year license term was selected on the basis of economic and antitrust considerations rather than technical limitations. Henceforth, many plants have sought (and obtained) a 20-year life extension. In

Reported issue

This section will provide detailed information on the first reported nuclear power plant in the U.S. known to possibly suffer from ASR. All information reported has been gathered exclusively from the ADAMS, the official record-keeping system through which the U.S. Nuclear Regulatory Commission provides access to publicly available documents. It is worth mentioning that ML121250588 (2012) does outline the regulatory framework and general acceptance criterion for NRC oversight and review.

  • Description

    NextEra

Conclusions

In summary, the authors agree that indeed “Seabrook ASR affected structures are operable but degraded” (ML121220109, 2012), however given the uncertainty of the rate and extent of degradation a major challenge is to anticipate the evolution of the reaction, and more importantly, its impact on the structural integrity of the reactor (both serviceability and strength). Answer to this critical question requires an uncompromising understanding of the State of the Art to properly and safely propose

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