Published 2016 | Version v1
Miscellaneous Metadata-only

US progress on property characterization to support LEU U-10 MO monolithic fuel development

Creators

  • 1. Nuclear Fuels and Materials Division, Idaho National Laboratory, PO box 1625 MS 3818, Idaho Falls, ID 83415-3818 (United States)

Description

The US High Performance Research Reactor program is pursuing development and qualification of a new high-density monolithic LEU fuel to facilitate conversion of five higher power research reactors (ATR, HFIR, NBSR, MIT and MURR) and one critical facility (ATR-C) located in the US. In order to support fabrication development and fuel performance evaluations, new testing capabilities are being developed to evaluate the properties of fuel specimens. Residual stress and fuel-cladding bond strength are two characteristics related to fuel performance that are being investigated. In this overview, new measurement capabilities being developed to assess these characteristics in both fresh and irradiated fuel are described. Progress on fresh fuel testing is summarized and on-going hot-cell implementation efforts to support future PIE campaigns are detailed. It is anticipated that benchmarking of as-fabricated fuel characteristics will be critical to establishing technical bases for specifications that optimize fuel fabrication and ensure acceptable in-reactor fuel performance. (author)

Part of:
European Research Reactor Conference (RRFM) 2016: Conference Proceedings

Additional details

Identifiers

URL
https://www.euronuclear.org/meetings/rrfm2016/transactions/rrfm2016-transactions.pdf;

Publishing Information

Publisher
European Nuclear Society
Imprint Place
Brussels (Belgium)
ISBN
978-92-95064-25-6
Imprint Title
European Research Reactor Conference (RRFM) 2016: Conference Proceedings
Imprint Pagination
1154 p.
Journal Page Range
p. 139-145
Report number
INIS-BE--16M5704

Conference

Title
20. international topical meeting on Research Reactor Fuel Management (RRFM)
Acronym
RRFM 2016
Dates
13-17 Mar 2016
Place
Berlin (Germany)

INIS

Country of Publication
Belgium
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
49023195
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ATR REACTOR; ATRC REACTOR; BENCHMARKS; CLADDING; FABRICATION; HFIR REACTOR; HOT CELLS; IRRADIATION; MITR REACTOR; MURR REACTOR; NBSR REACTOR; RESIDUAL STRESSES; SLIGHTLY ENRICHED URANIUM; SPENT FUELS; URANIUM-MOLYBDENUM FUELS
Descriptors DEC
ACTINIDES; ALLOY NUCLEAR FUELS; DEPOSITION; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM; ENRICHED URANIUM REACTORS; EQUIPMENT; EXPERIMENTAL REACTORS; FUELS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; IRRADIATION REACTORS; ISOTOPE ENRICHED MATERIALS; ISOTOPE PRODUCTION REACTORS; LABORATORY EQUIPMENT; MATERIALS; MATERIALS TESTING REACTORS; METALS; NUCLEAR FUELS; POOL TYPE REACTORS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SOLID FUELS; STRESSES; SURFACE COATING; TANK TYPE REACTORS; TEST FACILITIES; TEST REACTORS; THERMAL REACTORS; TRAINING REACTORS; URANIUM; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
© European Nuclear Society, 2003; 9 refs., 5 figs.; This record replaces 48058130
Secondary number(s)
RRFM2016--A0215