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Title: Electrochemical Corrosion Testing of Neutron Absorber Materials

Abstract

This report summarizes the results of crevice-corrosion tests for six alloys in solutions representative of ionic compositions inside the Yucca Mountain waste package should a breech occur. The alloys in these tests are Neutronit A978a (ingot metallurgy, hot rolled), Neutrosorb Plus 304B4 Grade Ab (powder metallurgy, hot rolled), Neutrosorb Plus 304B5 Grade Ab (powder metallurgy, hot rolled), Neutrosorb Plus 304B6 Grade Ab (powder metallurgy, hot rolled), Ni-Cr-Mo-Gd alloy2 (ingot metallurgy, hot rolled), and Alloy 22 (ingot metallurgy, hot rolled).

Authors:
; ; ;
Publication Date:
Research Org.:
Idaho National Laboratory (INL)
Sponsoring Org.:
DOE - RW
OSTI Identifier:
912462
Report Number(s):
INL/EXT-06-11772
TRN: US0800411
DOE Contract Number:
DE-AC07-99ID-13727
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
99 - GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE, 36 - MATERIALS SCIENCE; ALLOYS; CREVICE CORROSION; ELECTROCHEMICAL CORROSION; IONIC COMPOSITION; METALLURGY; NEUTRON ABSORBERS; TESTING; WASTES; YUCCA MOUNTAIN; corrosion testing; neutron absorber materials

Citation Formats

Tedd Lister, Ron Mizia, Arnold Erickson, and Tammy Trowbridge. Electrochemical Corrosion Testing of Neutron Absorber Materials. United States: N. p., 2007. Web. doi:10.2172/912462.
Tedd Lister, Ron Mizia, Arnold Erickson, & Tammy Trowbridge. Electrochemical Corrosion Testing of Neutron Absorber Materials. United States. doi:10.2172/912462.
Tedd Lister, Ron Mizia, Arnold Erickson, and Tammy Trowbridge. Tue . "Electrochemical Corrosion Testing of Neutron Absorber Materials". United States. doi:10.2172/912462. https://www.osti.gov/servlets/purl/912462.
@article{osti_912462,
title = {Electrochemical Corrosion Testing of Neutron Absorber Materials},
author = {Tedd Lister and Ron Mizia and Arnold Erickson and Tammy Trowbridge},
abstractNote = {This report summarizes the results of crevice-corrosion tests for six alloys in solutions representative of ionic compositions inside the Yucca Mountain waste package should a breech occur. The alloys in these tests are Neutronit A978a (ingot metallurgy, hot rolled), Neutrosorb Plus 304B4 Grade Ab (powder metallurgy, hot rolled), Neutrosorb Plus 304B5 Grade Ab (powder metallurgy, hot rolled), Neutrosorb Plus 304B6 Grade Ab (powder metallurgy, hot rolled), Ni-Cr-Mo-Gd alloy2 (ingot metallurgy, hot rolled), and Alloy 22 (ingot metallurgy, hot rolled).},
doi = {10.2172/912462},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue May 01 00:00:00 EDT 2007},
month = {Tue May 01 00:00:00 EDT 2007}
}

Technical Report:

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  • abstract
  • This report presents the results of the corrosion rates that were measured using electrochemical methods for tanks 241-AN-102 (AN-102), 241-AP-107 (AP 107), and 241-AP-108 (AP-108) performed under test plant RPP-PLAN-38215. The steel used as materials of construction for AN and AP tank farms was A537 Class 1. Test coupons of A537 Class 1 carbon steel were used for corrosion testing in the AN-107, AP-107, and AP-108 tank waste. Supernate will be tested from AN-102, AP-107, and Ap-108. Saltcake testing was performed on AP-108 only.
  • The work described in this report is intended to provide manufacturers, designers, and installers with reliable corrosion compatibility data, meaningful maintenance schedule, and confidence in durability and performance of solar collector units. The corrosion behavior of Cu alloy 122, Al alloy 1100, mild steel 1010, and a ferritic stainless steel (alloy 444) was determined in a variety of potential solar heat transfer fluids. The fluids included potable waters, water glycol solutions, and four non-aqueous fluids. The test apparatus cycled the temperatures of the fluids through those typical of an operating solar energy collector unit. The 444 stainless steel was themore » most corrosion resistant material and in uninhibited solutions demonstrated only extremely shallow pits during the 180 day test. The use of inhibited solutions generally prevented pits from forming. Cu alloy 122 showed quite low corrosion rates in uninhibited solutions although the presence of excess solder flux promoted some crevice corrosion. In such solutions, uniform, corrosive attack produced general surface roughening along with a protective surface oxide. The overall corrosion rate of the alloy was generally lower in inhibited glycol solutions although pitting within the crevice region occurred in limited cases. Exposure in the non-aqueous fluids resulted in extremely low corrosion rates with little evidence of localized attack.« less
  • This activity plan is prepared in accordance with Lawrence Livermore National Laboratory (LLNL) Yucca Mountain Project procedure 033.YMP-QP 3.0, "Scientific Investigation Control." This plan is written for activity E-20-46, entitled "Galvanic Corrosion Testing," which is a part of the Scientific Investigation Plan (SIP) "Metal Barrier Selection and Testing" (SIP-CM-01, Rev 2, CN SIP-CM-01-2-l).
  • The Department of Energy Office of Civilian Radioactive Waste Management has specified borated stainless steel manufactured to the requirements of ASTM A 887-89, Grade A, UNS S30464, to be the material used for the fabrication of the fuel basket internals of the preliminary transportation, aging, and disposal canister system preliminary design. The long-term corrosion resistance performance of this class of borated materials must be verified when exposed to expected YMP repository conditions after a waste package breach. Electrochemical corrosion tests were performed on crevice corrosion coupons of Type 304 B4 and Type 304 B5 borated stainless steels exposed to singlemore » postulated in-package chemistry at 60°C. The results show low corrosion rates for the test period« less