Cart (0)
  • No items in cart.
Subtotal
$0
There is a technical issue about last added item. You can click "Report to us" button to let us know and we resolve the issue and return back to you or you can continue without last item via click to continue button.
Search book title
Enter keywords for book title search
Search book content
Enter keywords for book content search
Filters:
FORMAT
BOOKS
PACKAGES
EDITION
to
PUBLISHER
(1)
(316)
(569)
(43)
(234)
(969)
(643)
(1935)
(64)
(91921)
(54)
(535)
(117)
(28)
(20)
(19)
(92193)
(3)
(17)
(1)
(351)
(298)
(6023)
(239)
(16)
(5)
(1619)
(16)
(18)
(28)
(4)
 
(6)
(7)
(115)
(3)
(57)
(5)
(5)
(1)
(1)
(2)
(23)
(26)
(27)
(13)
(61)
(24)
(22)
(7)
(8)
(20)
(1)
(3)
(50)
(6)
(31)
CONTENT TYPE
 Act
 Admin Code
 Announcements
 Bill
 Book
 CADD File
 CAN
 CEU
 Charter
 Checklist
 City Code
 Code
 Commentary
 Comprehensive Plan
 Conference Paper
 County Code
 Course
 DHS Documents
 Document
 Errata
 Executive Regulation
 Federal Guideline
 Firm Content
 Guideline
 Handbook
 Interpretation
 Journal
 Land Use and Development
 Law
 Legislative Rule
 Local Amendment
 Local Code
 Local Document
 Local Regulation
 Local Standards
 Manual
 Model Code
 Model Standard
 Notice
 Ordinance
 Other
 Paperback
 PASS
 Periodicals
 PIN
 Plan
 Policy
 Product
 Program
 Provisions
 Requirements
 Revisions
 Rules & Regulations
 Standards
 State Amendment
 State Code
 State Manual
 State Plan
 State Standards
 Statute
 Study Guide
 Supplement
 Technical Bulletin
 All
  • ASTM
    C1431-99(2005) Standard Guide for Corrosion Testing of Aluminum-Based Spent Nuclear Fuel in Support of Repository Disposal
    Edition: 2005
    $93.60
    Unlimited Users per year

Description of ASTM-C1431 2005

ASTM C1431-99(2005)

Historical Standard: ASTM C1431-99(2005) Standard Guide for Corrosion Testing of Aluminum-Based Spent Nuclear Fuel in Support of Repository Disposal

SUPERSEDED (see Active link, below)




ASTM C1431

1. Scope

1.1 This guide covers corrosion testing of aluminum-based spent nuclear fuel in support of geologic repository disposal (per the requirements in 10 CFR 60 and 40 CFR 191). The testing described in this document is designed to provide data for analysis of the chemical stability and radionuclide release behavior of aluminum-based waste forms produced from aluminum-based spent nuclear fuels. The data and analyses from the corrosion testing will support the technical basis for inclusion of aluminum-based spent nuclear fuels in the repository source term. Interim storage and transportation of the spent fuel will precede geologic disposal; therefore, reference is also made to the requirements for interim storage (per 10 CFR 72) and transportation (per 10 CFR 71). The analyses that will be based on the data developed are also necessary to support the safety analyses reports (SARs) and performance assessments (PAs) for disposal systems.

1.2 Spent nuclear fuel that is not reprocessed must be safely managed prior to transportation to, and disposal in, a geologic repository. Placement is an interim storage facility may include direct placement of the irradiated fuel or treatment of the fuel prior to placement, or both. The aluminum-based waste forms may be required to be ready for geologic disposal, or road ready, prior to placement in extended interim storage. Interim storage facilities, in the United States, handle fuel from civilian commercial power reactors, defense nuclear materials production reactors, and research reactors. The research reactors include both foreign and domestic reactors. The aluminum-based fuels in the spent fuel inventory in the United States are primarily from defense reactors and from foreign and domestic research reactors. The aluminum-based spent fuel inventory includes several different fuel forms and levels of 235 U enrichment. Highly enriched fuels ( 235 U enrichment leves > 20%) are part of this inventory.

1.3 Knowledge of the corrosion behavior of aluminum-based spent nuclear fuels is required to ensure safety and to support licensing or other approval activities, or both, necessary for disposal in a geologic repository. The response fo the aluminum-based spent nuclear fuel waste form(s) to disposal environments must be established for configuration-safety analyses, criticality analyses, PAs, and other analyses required to assess storage, treatment, transportation, and disposal of spent nuclear fuels. This is particularly important for the highly enriched, aluminum-based spent nuclear fuels. The test protocols described in this guide are designed to establish material response under the repository relevant conditions.

1.4 The majority of the aluminum-based spent nuclear fuels are aluminum clad, aluminum-uranium alloys. The aluminum-uranium alloy typically consists of uranium aluminide particles dispersed in an aluminum matrix. Other aluminum-based fuels include dispersions of uranium oxide, uranium silicide, or uranium carbide particles in an aluminum matrix. These particles, including the aluminides, are generally cathodic to the aluminum matrix. Selective leaching of the aluminum in the exposure environment may provide a mechanism for redistribution and relocation of the uranium-rich particles. Particle redistribution tendencies will depend on the nature of the aluminum corrosion processes and the size, shape, distribution and relative reactivity of the uranium-rich particles. Interpretation of test data will require an understanding of the material behavior. This understanding will enable evaluation of the design and configuration of the waste package to ensure that unfilled regions in the waste package do not provide sites for the relocation of the uranium-rich particles into nuclear critical configurations. Test samples must be evaluated, prior to testing, to ensure that the size and shape of the uranium-rich particles in the test samples are representative of the particles in the waste form being evaluated.

1.5 The use of the data obtained by the testing described in this guide will be optimized to the extent the samples mimic the condition of the waste form during actual repository exposure. The use of Practice C 1174 is recommended for guidance. The selection of test samples, which may be unaged or artificially aged, should ensure that the test samples and conditions bound the waste form/repository conditions. The test procedures should carefully describe any artificial aging treatment used in the test program and explain why that treatment was selected.


2. Referenced Documents (purchase separately) The documents listed below are referenced within the subject standard but are not provided as part of the standard.

ASTM Standards

C1174 Practice for Prediction of the Long-Term Behavior of Materials, Including Waste Forms, Used in Engineered Barrier Systems (EBS) for Geological Disposal of High-Level Radioactive Waste

Government Documents

10CFR72 US Code of Federal Regulations Title 10, Part 72, Licensing Requirements for the Independent Storage of Spent Nuclear and High-Level Radioactive Waste

Keywords

Corrosion--nuclear applications; Coupon corrosion testing; Electrochemical measurements/testing; Field testing--environmental materials/applications; Repository disposal; Spent nuclear fuels (SNF);


ICS Code

ICS Number Code 27.120.30 (Fissile materials and nuclear fuel technology)


DOI: 10.1520/C1431-99R05

ASTM International is a member of CrossRef.


This book also exists in the following packages...

Year Publisher Title Annual Price
VAR
ASTM
[+] $1,152.58 Buy
VAR
ASTM
[+] $1,737.94 Buy

Subscription Information

MADCAD.com ASTM Standards subscriptions are annual and access is unlimited concurrency based (number of people that can access the subscription at any given time) from single office location. For pricing on multiple office location ASTM Standards Subscriptions, please contact us at info@madcad.com or +1 800.798.9296.

 

Some features of MADCAD.com ASTM Standards Subscriptions are:

- Online access: With MADCAD.com’ s web based subscription service no downloads or installations are required. Access ASTM Standards from any browser on your computer, tablet or smart phone.

- Immediate Access: As soon as the transaction is completed, your ASTM Standards Subscription will be ready for access.

 

For any further information on MADCAD.com ASTM Standards Subscriptions, please contact us at info@madcad.com or +1 800.798.9296.

 

About ASTM

ASTM International, formerly known as the American Society for Testing and Materials (ASTM), is a globally recognized leader in the development and delivery of international voluntary consensus standards. Today, some 12,000 ASTM standards are used around the world to improve product quality, enhance safety, facilitate market access and trade, and build consumer confidence. ASTM’s leadership in international standards development is driven by the contributions of its members: more than 30,000 of the world’s top technical experts and business professionals representing 150 countries. Working in an open and transparent process and using ASTM’s advanced electronic infrastructure, ASTM members deliver the test methods, specifications, guides, and practices that support industries and governments worldwide.

X