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Title: TREAT Transient Analysis Benchmarking for the HEU Core

This work was performed to support the feasibility study on the potential conversion of the Transient Reactor Test Facility (TREAT) at Idaho National Laboratory from the use of high enriched uranium (HEU) fuel to the use of low enriched uranium (LEU) fuel. The analyses were performed by the GTRI Reactor Conversion staff at the Argonne National Laboratory (ANL). The objective of this study was to benchmark the transient calculations against temperature-limited transients performed in the final operating HEU TREAT core configuration. The MCNP code was used to evaluate steady-state neutronics behavior, and the point kinetics code TREKIN was used to determine core power and energy during transients. The first part of the benchmarking process was to calculate with MCNP all the neutronic parameters required by TREKIN to simulate the transients: the transient rod-bank worth, the prompt neutron generation lifetime, the temperature reactivity feedback as a function of total core energy, and the core-average temperature and peak temperature as a functions of total core energy. The results of these calculations were compared against measurements or against reported values as documented in the available TREAT reports. The heating of the fuel was simulated as an adiabatic process. The reported values were extractedmore » from ANL reports, intra-laboratory memos and experiment logsheets and in some cases it was not clear if the values were based on measurements, on calculations or a combination of both. Therefore, it was decided to use the term “reported” values when referring to such data. The methods and results from the HEU core transient analyses will be used for the potential LEU core configurations to predict the converted (LEU) core’s performance.« less
Authors:
 [1] ;  [1] ;  [1]
  1. Argonne National Lab. (ANL), Argonne, IL (United States)
Publication Date:
OSTI Identifier:
1224988
Report Number(s):
ANL/GTRI/TM--14/11
121903; TRN: US1500842
DOE Contract Number:
AC02-06CH11357
Resource Type:
Technical Report
Research Org:
Argonne National Lab. (ANL), Argonne, IL (United States)
Sponsoring Org:
USDOE National Nuclear Security Administration (NNSA)
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; HIGHLY ENRICHED URANIUM; PROMPT NEUTRONS; TRANSIENTS; TREAT REACTOR; BENCHMARKS; COMPARATIVE EVALUATIONS; CONFIGURATION; CONVERSION; NUCLEAR FUELS; ADIABATIC PROCESSES; FEASIBILITY STUDIES; REACTIVITY COEFFICIENTS; STEADY-STATE CONDITIONS; HEATING; REACTOR KINETICS; LIFETIME; PEAKS; PERFORMANCE; CONTROL ROD WORTHS; TEMPERATURE DISTRIBUTION; REACTOR CORES; ENERGY DEPENDENCE; COMPUTERIZED SIMULATION; SLIGHTLY ENRICHED URANIUM HEU; MCNP; benchmarking