AMPP Store - Products tagged with 'nuclear'

Available for download

09090601 Condition for Lead-Induced Corrosion of Alloy 690 in an Alkaline Steam Generator Crevice Solution

Product Number: 32141-09090601-SG

ISBN: 09090601CJ

Author: B.T. Lu, J.L. Luo, B. Peng, A. Palani, and Y.C. Lu

Publication Date: 2009

$13.00

The effects of dissolved lead on the anodic dissolution behavior of Alloy 690 (UNS N06690) were experimentally investigated in an alkaline solution that is used to simulate the environment in a nuclear steam generator crevice.

Available for download

51318-10516-Properties of Brines formed by Deliquescence of Sea-Salt Aerosols

Product Number: 51318-10516-SG

Author: C. R. Bryan / E.J. Schindelholz

Publication Date: 2018

$20.00

We have used thermodynamic modeling to predict the chemical composition of the brines that form by deliquescence of sea-salt aerosols, and to estimate brine volumes and salt/brine volume ratios as a function of temperature and atmospheric relative humidity.

Available for download

51318-10530-The Nuclear Energy Agency Contribution to Nuclear Materials Performance Knowledge Preservation

Product Number: 51318-10530-SG

Author: B.O.Y. Lydell / O. Nevander / J. Riznic

Publication Date: 2018

$20.00

The goal of The Nuclear Energy Agency (NEA) is to assist its member countries in ensuring safety, through regulation and oversight of nuclear installations, and to preserve the scientific and technological knowledge base.

Development And Application Of A Thermochemical Database (MSTDB-TC) To Modeling Corrosion In Molten Salt Reactors

Product Number: ED22-17137-SG

Author: Theodore M. Besmann, Jacob A. Yingling, Johnathan C. Ard, Matthew S. Christian, Amir M. Mofrad, Juliano Schorne Pinto, Mahmoud A. A. Aslani

Publication Date: 2022

$20.00

Accurate representations of the thermochemistry and phase equilibria of relevant molten salt constituents and their aggregate behavior are critical to the development, design, operation, and licensing of any molten salt reactor (MSR). This need is currently being addressed by the creation of a dedicated, high quality/validated MSR thermochemical database, the Molten Salt Thermal Properties Database-Thermochemical (MSTDB-TC). MSTDB-TC is being populated with prioritized models and values for vapor species, and liquid and crystalline phases of chloride and fluoride fuel and coolant salts with relevant fission product and transuranic elements, and more recently with corrosion-relevant systems with chromium, iron, and nickel. Multi-cation crystalline and melt solution models are being incorporated, including newly developed relations as necessary, to obtain real system behavior.

Available for download

Diffusion Limited Oxidation of XLPE Nuclear Electrical Cable Insulation

Product Number: ED22-17263-SG

Author: M. Spencer, D. Li, M.R. Pallaka, L.S. Fifield, W.K Fuchs, Y. Ni, A. Zwoster

Publication Date: 2022

$20.00

Approximately 20% of the electricity produced in the United States (U.S.) comes from nuclear power plants (NPPs). Originally, U.S. NPPs were qualified for an operational lifetime of 40 years and NPPs can apply for 20-year license extensions following the original 40-year operating period. While most NPPs have entered extended license periods to 60 years, some are considering license extension to 80 years of operation. The viability of a subsequent license renewal (SLR) is dependent upon NPPs operating safely in accordance with a licensing basis similar to that established with the original 40-year license.

Available for download

Evaluation Of Copper Catalytic Effects In Cable Insulation Polymers

Product Number: ED22-17260-SG

Author: Trevor Toll, Casey Sexton, Codi Ferree, Patrick Ward

Publication Date: 2022

$20.00

This paper summarizes work performed to evaluate a phenomenon that can occur in electrical cable insulation polymers during the aging process. This phenomenon, the copper catalytic effect, occurs because of diffusion of copper ions from the conductor into the insulation polymers during the aging process. In this research, the copper catalytic effects observed in cross-linked polyethylene, cross-linked polyolefin, and ethylene propylene rubber insulation subjected to thermal accelerated aging at both 120˚C and 130 ˚C were evaluated. In addition, the insulation polymers from cables removed from service in operating nuclear power plants were also evaluated to determine if this effect is prevalent for naturally aged materials. The results acquired from this work were used to characterize the copper catalytic effects observed in these polymers, analyze how this phenomenon affects the degradation process of the materials, and determine the impact that the copper catalytic effect has on condition monitoring data acquired during the aging process.

Available for download

Examination Of A Ferritic Martensitic Steel Following Irradiation And High Temperature Water Corrosion

Product Number: 51322-18127-SG

Author: Ronald N. Clark, Tomas Martin, Dong Liu, Kun Mo, Jean-Charles Eloi, Robert Burrows, Sean Davis, David Kumar, Chris Harrington, Chris Jones

Publication Date: 2022

$20.00

Nuclear energy currently contributes approximately 10 % of the worldwide energy mix.¹ Nuclear energy generation is a form of low-carbon electricity, typically run as base-load, which alongside renewables can help nations toward climate change goals. Nuclear fission thermal reactors make up the majority of the reactors operating today. Nuclear fusion on the other hand is a promising alternative which produces less radioactive waste and does not have a reliance on the finite source of uranium fuel. Eurofer-97, a reduced activation ferritic-martensitic (RAFM) steel, will be used as a structural material for fusion reactors. The earliest literature reference to RAFM steels originated from 1994 by Abe et al.² One option for the European demonstration fusion reactor (DEMO) is to use a water-cooled lead-lithium (PbLi) breeder blanket (WCLL BB) design for heat extraction. Breeder blankets will be used to generate a source of tritium, for the fusion reaction with deuterium.

Available for download

Hydrogen Cracks in Belgian Nuclear Reactor Pressure Vessels: Five Years After Their Discovery

Product Number: 51317--9457-SG

ISBN: 9457 2017 CP

Author: Walter Bogaerts

Publication Date: 2017

$20.00

Elaborates on some reported findings and identifies possible mechanisms and risks for further growth of defects in the reactor pressure vessel walls in the Belgian nuclear power reactors Doel 3 and Tihange 2 – which were restarted in 2015 after inspection found “thousands” of “hydrogen flaws”.

Available for download

Life Beyond 80: Can Concrete Degradation’ Synergetic Modes Become Showstoppers for Light Water Reactors?

Product Number: ED22-17261-SG

Author: Yann Le Pape, Elena Tajuelo Rodriguez, Bethel Amani Cheniour, Mohammed Alnaggar, Paula Bran Anleu, Thomas M. Rosseel, David Arregui Mena, Adam Brooks

Publication Date: 2022

$20.00

The US light water reactor (LWR) fleet is a strategic US asset for meeting the demand for clean, sustained, and affordable energy. Extended operations are governed by endogenous (e.g., aging management, operation costs) and exogenous (e.g., natural gas, deployment of advanced nuclear reactors) economic factors but also by technical issues associated with doubling the original 40 year license period. Materials aging includes all critical components of the reactors, such as internals, reactor pressure vessel, cabling, and concrete structures.

Available for download

NACE Publication 41013-2013-SG, "State-of-the-Art Report: External Corrosion, Assessment and Control of Buried Piping Systems in Nuclear Power Plants"

Product Number: 24252-SG

Publication Date: 2013

$109.00

Recent experience from nuclear power plants indicates that degradation of buried piping is occurring in at least some plants and represents an issue requiring the attention of the nuclear industry.

Available for download

SP0515-2015-SG, “Implementing Nondestructive Evaluation Technologies to Evaluate Buried Pipe in Nuclear Power Plants”

Product Number: 21196-SG

ISBN: 1-57590-317-2

Publication Date: 2015

$109.00

For those managing, planning, selecting, implementing, or evaluating buried pipe inspections using Non-Destructive Evaluation (NDE) at nuclear power plant sites. Licensing. Regulations. Inspection. Tools. Analysis.

Available for download

Stress Corrosion Cracking Behaviour Of Thermally Aged Alloy 182

Product Number: ED22-17291-SG

Author: Siddharth Suman, Hans-Peter Seifert, Philippe Spätig, Stefan Ritter

Publication Date: 2022

$20.00

Alloy 182 is an austenitic (FCC) nickel base Ni-Cr-Fe-Mn weld metal that is used as a weld filler or weld pad metal to join stainless steel reactor internals, reactor instrumentation penetrations and main coolant piping to the low-alloy steel reactor pressure vessel. Stress corrosion cracking (SCC) in alloy 182 dissimilar welds is one of the most important material degradation problems and an ongoing issue in boiling (BWR) and pressurized water reactors (PWR) world-wide with potential safety concerns.
Thermally activated preferential local ordering (unlike atom pairs is greater than that in a random solution) of elements within a lattice, over spatial dimensions that are typically on the order of a few nearest neighbor spacing 20 to 50 Å (2 to 5 nm) is referred as short range ordering (SRO). SRO causes lattice contraction and induces additional stress which is claimed as the driving force for SCC in the alloy 600, alloy 690, and alloy 182.

Products tagged with 'nuclear'

Association for Materials Protection and Performance