The Corrosion of Aluminum Alloys in the Oak Ridge Research Reactor

The Corrosion of Aluminum Alloys in the Oak Ridge Research Reactor
Author:
Publisher:
Total Pages:
Release: 1961
Genre:
ISBN:

A corrosion testing program designed to estimate the potential service life of aluminum alloys used in the construction of the Oak Ridge Research Reactor (ORR) cooling systems has been in progress for over two years. The five alloys (1100, 3003, 5052, 5154, and 6061) used to the greatest extent in the reactor exhibited continuously decreasing corrosion rates since the first 500-hr inspection. Samples exposed in the core-cooling loop have shown a decrease in corrosion rate from a 2.6 mpy maximum for one group during the first 500 hr to an over-all average of less than 0.1 mpy for another group after a full year in test, with the maximum metal loss less than 0.1 mils. Results indicate that with suitable water treatment the aluminum alloys used in the ORR may be expected to give satisfactory performance for many years. Based on the generalized corrosion rates alone, 40 to 50 years of service life may be expected. However, since occasional localized corrosion has been observed (rarely), minor repairs will almost certainly be required before that time. (auth).

Corrosion in the Oak Ridge Research Reactor Core-Cooling System

Corrosion in the Oak Ridge Research Reactor Core-Cooling System
Author:
Publisher:
Total Pages:
Release: 1960
Genre:
ISBN:

Corrosion specimens of the five major aluminum alloys used in the construction of the Oak Ridge Research Reactor have been exposed to the high- purity primary cooling water in the ORR core and in the extennal portion of the primary cooling loop to determine their corrosion rates under actual operating conditions. These alloys, 1100, 3003, 5052, 5154. and 8061, exhibited average corrosion rates of less than 2.6 mpy during the first 500-hr test period and less than 0.5 mpy for a 4032-hr test. Very superficial pitting was observed. and no case of intergranular corrosion was found. (auth).

Aluminum Alloy Corrosion

Aluminum Alloy Corrosion
Author:
Publisher:
Total Pages:
Release: 1962
Genre:
ISBN:

To be published in TID-7642 Proceedings of the Conference on Research Reactors, held in Gatlinburg, Tenn., Sept. 17-19, 1982. The dynamic corrosion of all the aluminum alloys tested has proven to be particularly sensitive to testing parameters in the 200-325 deg C temperature range. Frequently it is difficult to reproduce corrosion data in a given dynamic test loop, while variations from laboratorv to laboratory have shown rate factors of 25 or more for the same nominal conditions of temperature and velocity. Several hypotheses have now been proposed to account for these variations. An attempt is made to examine some potertial research reactor corrosion problems in terms of predictions of the hypotheses. The effect of the high level of radiation encountered in such reactors is an unknown factor and only a full scale in- reactor test can provide final answers. (R.J.S.).

Corrosion of Research Reactor Aluminium Clad Spent Fuel in Water

Corrosion of Research Reactor Aluminium Clad Spent Fuel in Water
Author: International Atomic Energy Agency
Publisher:
Total Pages: 236
Release: 2003
Genre: Business & Economics
ISBN:

This report describes research performed in ten laboratories within the framework of the IAEA Co-ordinated Research Project on Corrosion of Research Reactor Aluminium Clad Spent Fuel in Water. The project consisted of exposure of standard racks of corrosion coupons in the spent fuel pools of the participating research reactor laboratories and evaluation of the coupons after predetermined exposure times, along with periodic monitoring of the storage water. A group of experts in the field contributed a state of the art review and provided technical supervision of the project. Localized corrosion mechanisms are notoriously difficult to understand, and it was clear from the outset that obtaining consistency in the results and their interpretation from laboratory to laboratory would depend on the development of an excellent set of experimental protocols. These experimental protocols are described in the report, together with guidelines for the maintenance of optimum water chemistry to minimize the corrosion of aluminium clad research reactor fuel in wet storage.

Proceedings

Proceedings
Author:
Publisher:
Total Pages: 484
Release: 1963
Genre: Nuclear reactors
ISBN:

Comprehensive Nuclear Materials

Comprehensive Nuclear Materials
Author:
Publisher: Elsevier
Total Pages: 4871
Release: 2020-07-22
Genre: Science
ISBN: 0081028660

Materials in a nuclear environment are exposed to extreme conditions of radiation, temperature and/or corrosion, and in many cases the combination of these makes the material behavior very different from conventional materials. This is evident for the four major technological challenges the nuclear technology domain is facing currently: (i) long-term operation of existing Generation II nuclear power plants, (ii) the design of the next generation reactors (Generation IV), (iii) the construction of the ITER fusion reactor in Cadarache (France), (iv) and the intermediate and final disposal of nuclear waste. In order to address these challenges, engineers and designers need to know the properties of a wide variety of materials under these conditions and to understand the underlying processes affecting changes in their behavior, in order to assess their performance and to determine the limits of operation. Comprehensive Nuclear Materials, Second Edition, Seven Volume Set provides broad ranging, validated summaries of all the major topics in the field of nuclear material research for fission as well as fusion reactor systems. Attention is given to the fundamental scientific aspects of nuclear materials: fuel and structural materials for fission reactors, waste materials, and materials for fusion reactors. The articles are written at a level that allows undergraduate students to understand the material, while providing active researchers with a ready reference resource of information. Most of the chapters from the first Edition have been revised and updated and a significant number of new topics are covered in completely new material. During the ten years between the two editions, the challenge for applications of nuclear materials has been significantly impacted by world events, public awareness, and technological innovation. Materials play a key role as enablers of new technologies, and we trust that this new edition of Comprehensive Nuclear Materials has captured the key recent developments. Critically reviews the major classes and functions of materials, supporting the selection, assessment, validation and engineering of materials in extreme nuclear environments Comprehensive resource for up-to-date and authoritative information which is not always available elsewhere, even in journals Provides an in-depth treatment of materials modeling and simulation, with a specific focus on nuclear issues Serves as an excellent entry point for students and researchers new to the field