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ASTM C 1010 : 1983 : R1992 : EDT 1

Withdrawn

Withdrawn

A Withdrawn Standard is one, which is removed from sale, and its unique number can no longer be used. The Standard can be withdrawn and not replaced, or it can be withdrawn and replaced by a Standard with a different number.

Standard Guide for Acceptance, Checkout, and Pre-Operational Testing of a Nuclear Fuels Reprocessing Facility (Withdrawn 2001)

Available format(s)

Hardcopy , PDF

Withdrawn date

01-01-2001

Language(s)

English

Published date

31-12-2010

€59.22
Excluding VAT

Committee
C 26
DocumentType
Guide
Pages
4
ProductNote
e1NOTE—Section 10, Keywords, was added editorially in November 1992
PublisherName
American Society for Testing and Materials
Status
Withdrawn

1.1 This guide sets forth those criteria necessary for the acceptance, checkout, and pre-operational testing of a nuclear fuels reprocessing facility.

1.2 This guide is specifically applicable to a nuclear fuels reprocessing facility employing the Purex process; however, a large portion of this guide is also applicable to other facilities employing different processes.

1.3 This guide provides recommendations for procedure preparation, acceptance criteria following construction, training, component and systems tests, and final integrated testing. These procedures when utilized in accordance with the prescribed quality assurance (QA) requirements should provide permanent QA records.

1.4 This guide deals primarily with the mainline aqueous/ organic (Purex) sections of a nuclear fuels reprocessing facility. Operations such as fuel receipt, headend (shearing and dissolution), plutonium conversion, waste immobilization, and others of this nature are not included.

1.5 This standard does not purport to address all of the safety problems, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

ASTM C 1062 : 2000 : R2014 Standard Guide for Design, Fabrication, and Installation of Nuclear Fuel Dissolution Facilities

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