Development of axial and ring hoop tension testing methods for nuclear fuel cladding tubes
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Kamerman, David↗
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Results for “cladding”
Search indexed NASA NTRS and DOE OSTI research on propulsion, heat transfer, battery materials and energy systems. Follow report and document links to the original sources.
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System code evaluation of near-term accident tolerant claddings during boiling water reactor short-term and long-term station blackout accidents
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Nuclear Science & Technology↗
Quantification of the effect of Cr-coated-Zircaloy cladding during a short term station black out
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Feng, Tangtao (ORCID:0000000228291765)↗
Accident tolerant fuels (FeCrAl Cladding & Coating) performance analysis in Boiling Water Reactor (BWR) by the MELCOR 1.8.6 UDGC
Not Available
Wang, Jun (ORCID:0000000245504603)↗
Study of neutronic and creep properties of Kanthal APMT for advanced fuel cladding applications
Not Available
Pradhan, Arnold↗
Distribution of metallic fission-product particles in the cladding liner of spent nuclear fuel
Not Available
36 MATERIALS SCIENCE↗
Fabrication of Sol Gel Derived Cladding for Sapphire Fibers and Their Performance Evaluation Under Harsh Environment
SPIE Photonics West 2021 (Conference), Virtual, March 6-11, 2021
Bera, Subhabrata↗
Accelerated Fuel Qualification: BISON Validation to In-Situ Cladding Burst Test
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Capps, Nathan↗
TEV-3349 "ATF-2 2A Loop Pin Cladding Requirements"
Industry partners, including Westinghouse, Framatome, General Electric, General Atomics, Toshiba, etc. require requirements for fuel pins they insert in the reactor for testing. This document contains those requirements. These requirements represent an agreement between ATR and NS&T, and include the requirements for pins fabricated at the INL. These include inspections such as radiography, helium leak check, etc.
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
High Temperature Moderator Cladding Report
The hydrogen permeation system at LANL has been modified and improved to perform high temperature testing of metals and metal/ceramic samples. This will allow us to demonstrate the ability to reduce hydrogen permeation for microreactor materials. For this program, two metals have been chosen for analysis, stainless steel as a base metal and TZM based on its high temperature properties and anticipated higher H permeation resistance. Samples have been fabricated and coated with Al 2 O 3 via atomic layer deposition in order to evaluate the potential to reduce hydrogen permeation with a thin layer ceramic coating. Current efforts include literature review of systems and sample fabrication to demonstrate feasibility, future work will focus on collecting hydrogen permeation data.
22 GENERAL STUDIES OF NUCLEAR REACTORS↗
Technical Basis for Extended Dry Storage of Aluminum-Clad Spent Nuclear Fuel
This report addresses previously identified technical knowledge and technology gaps and presents the key findings of the multiyear, EMTD-funded research efforts with the goal of evaluating whether ASNF can be safely stored dry for many decades and whether changes to existing ASNF management practices are appropriate. The findings formulate the technical basis for the extended dry storage of ASNF, leading to the main conclusion: All completed work to close the identified knowledge gaps on extended (>50 years) ASNF dry storage supports the conclusion that extended ASNF dry storage is both safe and viable.
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗