New Ceramic Matrix Composites TG to Address Nuclear Energy Systems

Nuclear Power Standards

IEC 60880
Nuclear power plants – Instrumentation and control systems important to safety – Software aspects for computer-based systems performing category A functions-Edition 2.0

ASTM C 1638
Standard Guide for the Determination of Iodine-129 In Uranium Oxide

IEEE 1205
Guide for Assessing, Monitoring, and Mitigating Aging Effects on Class 1E Equipment Used in Nuclear Power Generating Stations

IEEE 344
Recommended Practice for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations

IEEE 1023
Recommended Practice for the Application of Human Factors Engineering to Systems, Equipment, and Facilities of Nuclear Power Generating Stations and Other Nuclear Facilities

ANS 55.6
Liquid Radioactive Waste Processing System For Light Water Reactor Plants

ANS 51.1
Nuclear Safety Criteria For Design Of Stationary Pressurized Water Reactor Plants

ANS 58.2
Design Basis For Protection Of Light Water Nuclear Power Plants Against The Effects Of Postulated Pipe Rupture

ANS 5.1
Decay Heat Power In Light Water Reactors

ANS 57.1
Design Requirements For Light Water Reactor Fuel Handling Systems

IEEE 352
IEEE Guide for General Principles of Reliability Analysis of Nuclear Power Generating Station Safety Systems

IEEE 933
IEEE Guide for the Definition of Reliability Program Plans for Nuclear Power Generating Stations

IEEE 1289
IEEE Guide for the Application of Human Factors Engineering in the Design of Computer-Based Monitoring and Control Displays for Nuclear Power Generating Stations

For other standards, regulations and documents, please visit the IHS standards store.

New Ceramic Matrix Composites TG to Address Nuclear Energy Systems

March 30, 2005

Power & Utilities Documents

IHS sells standards collections and regulatory information for the nuclear power and utilities industries.
For more information and a price quote, please complete the form below.

To advance nuclear energy to meet future energy needs, 10 countries - Argentina, Brazil, Canada, France, Japan, the Republic of Korea, the Republic of South Africa, Switzerland, the United Kingdom, and the United States - agreed on a framework for international cooperation in research for a future generation of nuclear energy systems, known as Generation IV.

"Generation IV nuclear energy systems are an ensemble of nuclear reactor technologies that could be commercially deployed by 2030 and present significant improvements in economics, safety and reliability and sustainability over currently operating reactor technologies," said Edgar Lara-Curzio, leader of the Mechanical Properties and Mechanics Group at the Oak Ridge National Laboratory.

In the U.S., the leading concept among Generation IV systems is the next generation nuclear plant (NGNP), envisioned to be a high-temperature reactor cooled with either helium or a molten fluoride salt. The primary structural material candidates for control-rod guide tubes and control-rod structural elements in the helium-cooled NGNP include fiber-reinforced SiC/SiC composites because of the resistance of these materials to both high temperature and high radiation exposure.

Subcommittee C28.07 formed the new task group to address the development of standardized test methods for the thermomechanical evaluation of SiC/SiC and C/C tubular structures that would be used for control-rod guide tubes and control-rod structural elements in the NGNP.

The availability of such standards is essential to support the eventual development of design guides for the manufacture and qualification of the aforementioned components. The new task group also serves as a forum for the ongoing collaboration of researchers from the U.S. and France, who are participating in an International Nuclear Energy Research Initiative focused on the development of these components as part of Generation IV.

For further technical information, contact Edgar Lara-Curzio, Oak Ridge National Laboratory, at (865) 574-1749 or laracurzioe@ornl.gov.

For membership or meeting details, contact Carolyn Sheahan, ASTM International, at (610) 832-9804 or csheahan@astm.org.