Published September 12, 2001 | Version v1
Report Metadata-only

Prototypic irradiation testing of high-density U-Mo alloy dispersion fuels

Creators

Description

no abstract available

Availability note (English)

Available from PURL: https://www.osti.gov/servlets/purl/789682-Iq2eKv/native/

Additional details

Identifiers

URL
https://www.osti.gov/servlets/purl/789682-Iq2eKv/native/;

Publishing Information

Imprint Pagination
[vp.]
Report number
ANL/TD/CP--100246

Conference

Title
1999 International Meeting on Reduced Enrichment for Research and Test Reactors
Dates
3-8 Oct 1999
Place
Budapest (Hungary)

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
33004470
Subject category
S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, No Abstract, Non-conventional Literature
Descriptors DEI
DISPERSION NUCLEAR FUELS; IRRADIATION; MATERIALS TESTING; MOLYBDENUM ALLOYS; RESEARCH AND TEST REACTORS; URANIUM ALLOYS
Descriptors DEC
ACTINIDE ALLOYS; ALLOYS; ENERGY SOURCES; FUELS; MATERIALS; NUCLEAR FUELS; REACTOR MATERIALS; REACTORS; SOLID FUELS; TESTING; TRANSITION ELEMENT ALLOYS

Optional Information

Contract/Grant/Project number
W-31-109-ENG-38
Funding organization
US Department of Energy (United States)