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Title: M5 Alloy Specification for TREAT Conceptual Fuel Cladding Selection

Abstract

The Idaho National Laboratory (INL) Transient Reactor Test Facility (TREAT) is a nuclear test facility designed to provide safety data for fuel designs by simulating conditions during various types of nuclear excursions. The M5 alloy cladding material for the conceptual TREAT Low Enriched Uranium fuel core shall be supplied according to this specification.

Authors:
ORCiD logo [1]
  1. Idaho National Laboratory
Publication Date:
Research Org.:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org.:
C620
OSTI Identifier:
1484704
Report Number(s):
INL-MIS-18-50164-Rev000
DOE Contract Number:  
AC07-05ID14517
Resource Type:
Program Document
Country of Publication:
United States
Language:
English
Subject:
11 - NUCLEAR FUEL CYCLE AND FUEL MATERIALS; TREAT LEU Conversion; Zirconium Alloy; Cladding

Citation Formats

Parga, Clemente J. M5 Alloy Specification for TREAT Conceptual Fuel Cladding Selection. United States: N. p., 2018. Web.
Parga, Clemente J. M5 Alloy Specification for TREAT Conceptual Fuel Cladding Selection. United States.
Parga, Clemente J. Thu . "M5 Alloy Specification for TREAT Conceptual Fuel Cladding Selection". United States. https://www.osti.gov/servlets/purl/1484704.
@article{osti_1484704,
title = {M5 Alloy Specification for TREAT Conceptual Fuel Cladding Selection},
author = {Parga, Clemente J.},
abstractNote = {The Idaho National Laboratory (INL) Transient Reactor Test Facility (TREAT) is a nuclear test facility designed to provide safety data for fuel designs by simulating conditions during various types of nuclear excursions. The M5 alloy cladding material for the conceptual TREAT Low Enriched Uranium fuel core shall be supplied according to this specification.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2018},
month = {3}
}

Program Document:
Other availability
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