Published June 1, 2013 | Version v1
Report Metadata-only

Initial Neutronics Analyses for HEU to LEU Fuel Conversion of the Transient Reactor Test Facility (TREAT) at the Idaho National Laboratory

Creators

  • 1. Argonne National Lab. (ANL), Argonne, IL (United States)

Description

The purpose of the TREAT reactor is to generate large transient neutron pulses in test samples without over-heating the core to simulate fuel assembly accident conditions. The power transients in the present HEU core are inherently self-limiting such that the core prevents itself from overheating even in the event of a reactivity insertion accident. The objective of this study was to support the assessment of the feasibility of the TREAT core conversion based on the present reactor performance metrics and the technical specifications of the HEU core. The LEU fuel assembly studied had the same overall design, materials (UO2 particles finely dispersed in graphite) and impurities content as the HEU fuel assembly. The Monte Carlo N–Particle code (MCNP) and the point kinetics code TREKIN were used in the analyses.

Availability note (English)

Available from http://www.ipd.anl.gov/anlpubs/2015/10/121484.pdf; PURL: http://www.osti.gov/servlets/purl/1224971/

Additional details

Identifiers

URL
http://www.ipd.anl.gov/anlpubs/2015/10/121484.pdf; http://www.osti.gov/servlets/purl/1224971/;

Publishing Information

Imprint Pagination
94 p.
Report number
ANL/GTRI/TM--13/4

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
47006286
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Non-conventional Literature
Descriptors DEI
CONVERSION; DESIGN; FEASIBILITY STUDIES; FUEL ASSEMBLIES; GRAPHITE; HEATING; HIGHLY ENRICHED URANIUM; MONTE CARLO METHOD; NUCLEAR FUELS; PARTICLES; REACTOR KINETICS; SLIGHTLY ENRICHED URANIUM; TREAT REACTOR; URANIUM DIOXIDE
Descriptors DEC
ACTINIDE COMPOUNDS; ACTINIDES; AIR COOLED REACTORS; CALCULATION METHODS; CARBON; CHALCOGENIDES; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; FUELS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HOMOGENEOUS REACTORS; ISOTOPE ENRICHED MATERIALS; KINETICS; MATERIALS; METALS; MINERALS; NONMETALS; OXIDES; OXYGEN COMPOUNDS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; SOLID HOMOGENEOUS REACTORS; TEST FACILITIES; TEST REACTORS; THERMAL REACTORS; URANIUM; URANIUM COMPOUNDS; URANIUM OXIDES

Optional Information

Contract/Grant/Project number
AC02-06CH11357
Funding organization
USDOE National Nuclear Security Administration (NNSA), Office of Defense Nuclear Nonproliferation (NA-20) (United States); Office of Material Management and Minimization (M3) (United States)
Secondary number(s)
OSTIID--1224971