Published September 30, 2015 | Version v1
Report Metadata-only

Modeling and Simulation of Used Nuclear Fuel During Transportation with Consideration of Hydride Effects and Cyclic Fatigue

Creators

  • 1. Idaho National Lab. (INL), Idaho Falls, ID (United States)
  • 2. STANEX (United States)

Description

The objective of this work is to understand the integrity of Used Nuclear Fuel (UNF) during transportation. Previous analysis work has been performed to look at the integrity of UNF during transportation but these analyses have neglected to analyze the effect of hydrides and flaws (fracture mechanics models to capture radial cracking in the cladding). In this study, the clad regions of interest are near the pellet-pellet interfaces. These regions can experience more complex stress-states than the rest of the clad during cooling and have a greater possibility to develop radially reoriented hydrides during vacuum drying.

Additional details

Identifiers

URL
http://www.osti.gov/servlets/purl/1238210/;

Publishing Information

Imprint Pagination
47 p.
Report number
INL/EXT--15-36697

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
47061244
Subject category
S42: ENGINEERING; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
Resource subtype / Literary indicator
Non-conventional Literature
Descriptors DEI
COOLING; CRACKS; DEFECTS; DRYING; FATIGUE; FRACTURE MECHANICS; FUEL CANS; HYDRIDES; INTERFACES; PELLETS; RAIL TRANSPORT; SIMULATION; SPENT FUELS; STRESSES
Descriptors DEC
ENERGY SOURCES; FUELS; HYDROGEN COMPOUNDS; LAND TRANSPORT; MATERIALS; MECHANICAL PROPERTIES; MECHANICS; NUCLEAR FUELS; REACTOR MATERIALS; TRANSPORT

Optional Information

Contract/Grant/Project number
AC07-05ID14517
Funding organization
USDOE Office of Nuclear Energy - NE (United States)
Secondary number(s)
OSTIID--1238210