Cart (0)
  • No items in cart.
Total
$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.
Filters:
EDITION
to
PUBLISHER
(1)
(353)
(651)
(599)
(58)
(290)
(1042)
(728)
(2262)
(117)
(97896)
(58)
(635)
(132)
(33)
(28)
(20)
(99791)
(18)
(1)
(396)
(328)
(10763)
(7369)
(252)
(21)
(24378)
(849)
(7)
(1722)
(23)
(19)
(28)
(4)
 
(6)
(7)
(128)
(1)
(3)
(58)
(5)
(5)
(1)
(1)
(2)
(28)
(27)
(36)
(13)
(71)
(24)
(25)
(7)
(8)
(20)
(1)
(3)
(50)
(6)
(34)
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
 Product - Data Sheet
 Program
 Provisions
 Requirements
 Revisions
 Rules & Regulations
 Standards
 State Amendment
 State Code
 State Manual
 State Plan
 State Standards
 Statute
 Study Guide
 Supplement
 Sustainability
 Technical Bulletin
 All
  • ISO
    ISO 19226:2017 Nuclear energy - Determination of neutron fluence and displacement per atom (dpa) in reactor vessel and internals
    Edition: 2017
    $192.38
    / user per year

Content Description

ISO 19226:2017 provides a procedure for the evaluation of irradiation data in the region between the reactor core and the inside surface of the containment vessel, through the pressure vessel and the reactor cavity, between the ends of active fuel assemblies, given the neutron source in the core.

NOTE These irradiation data could be neutron fluence or displacements per atom (dpa), and Helium production.

The evaluation employs both neutron flux computations and measurement data from in-vessel and cavity dosimetry, as appropriate. This document applies to pressurized water reactors (PWRs), boiling water reactors (BWRs), and pressurized heavy water reactors (PHWRs).

ISO 19226:2017 also provides a procedure for evaluating neutron damage properties at the reactor pressure vessel and internal components of PWRs, BWRs, and PHWRs. Damage properties are focused on atomic displacement damage caused by direct displacements of atoms due to collisions with neutrons and indirect damage caused by gas production, both of which are strongly dependent on the neutron energy spectrum. Therefore, for a given neutron fluence and neutron energy spectrum, calculations of the total accumulated number of atomic displacements are important data to be used for reactor life management.



About ISO

ISO, the International Organization for Standardization, brings global experts together to agree on the best way of doing things – for anything from making a product to managing a process. As one of the oldest non-governmental international organizations, ISO has enabled trade and cooperation between people and companies all over the world since 1946. The International Standards published by ISO serve to make lives easier, safer and better.

GROUPS