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Title: Transmutation Fuel Performance Code Conceptual Design

Abstract

One of the objectives of the Global Nuclear Energy Partnership (GNEP) is to facilitate the licensing and operation of Advanced Recycle Reactors (ARRs) for transmutation of the transuranic elements (TRU) present in spent fuel. A fuel performance code will be an essential element in the licensing process ensuring that behavior of the transmutation fuel elements in the reactor is understood and predictable. Even more important in the near term, a fuel performance code will assist substantially in the fuels research and development, design, irradiation testing and interpretation of the post-irradiation examination results.

Authors:
;
Publication Date:
Research Org.:
Idaho National Laboratory (INL)
Sponsoring Org.:
DOE - NE
OSTI Identifier:
911923
Report Number(s):
INL/EXT-07-12306
TRN: US0800215
DOE Contract Number:
DE-AC07-99ID-13727
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
11 - NUCLEAR FUEL CYCLE AND FUEL MATERIALS , 99 - GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE; DESIGN; FUEL ELEMENTS; IRRADIATION; LICENSING; NUCLEAR ENERGY; PERFORMANCE; POST-IRRADIATION EXAMINATION; SPENT FUELS; TESTING; TRANSMUTATION; fuel behavior model; GNEP; transmutation fuel

Citation Formats

Gregory K. Miller, and Pavel G. Medvedev. Transmutation Fuel Performance Code Conceptual Design. United States: N. p., 2007. Web. doi:10.2172/911923.
Gregory K. Miller, & Pavel G. Medvedev. Transmutation Fuel Performance Code Conceptual Design. United States. doi:10.2172/911923.
Gregory K. Miller, and Pavel G. Medvedev. Thu . "Transmutation Fuel Performance Code Conceptual Design". United States. doi:10.2172/911923. https://www.osti.gov/servlets/purl/911923.
@article{osti_911923,
title = {Transmutation Fuel Performance Code Conceptual Design},
author = {Gregory K. Miller and Pavel G. Medvedev},
abstractNote = {One of the objectives of the Global Nuclear Energy Partnership (GNEP) is to facilitate the licensing and operation of Advanced Recycle Reactors (ARRs) for transmutation of the transuranic elements (TRU) present in spent fuel. A fuel performance code will be an essential element in the licensing process ensuring that behavior of the transmutation fuel elements in the reactor is understood and predictable. Even more important in the near term, a fuel performance code will assist substantially in the fuels research and development, design, irradiation testing and interpretation of the post-irradiation examination results.},
doi = {10.2172/911923},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu Mar 01 00:00:00 EST 2007},
month = {Thu Mar 01 00:00:00 EST 2007}
}

Technical Report:

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  • FRAPCON fuel performance code is being modified to be able to model performance of the nuclear fuels of interest to the Global Nuclear Energy Partnership (GNEP). The present report documents the effort for verification of the FRAPCON thermal model. It was found that, with minor modifications, FRAPCON thermal model temperature calculation agrees with that of the commercial software ABAQUS (Version 6.4-4). This report outlines the methodology of the verification, code input, and calculation results.
  • A new mechanical model has been developed for implementation into the TRU fuel performance code. The new model differs from the existing FRAPCON 3 model, which it is intended to replace, in that it will include structural deformations (elasticity, plasticity, and creep) of the fuel. Also, the plasticity algorithm is based on the “plastic strain–total strain” approach, which should allow for more rapid and assured convergence. The model treats three situations relative to interaction between the fuel and cladding: (1) an open gap between the fuel and cladding, such that there is no contact, (2) contact between the fuel andmore » cladding where the contact pressure is below a threshold value, such that axial slippage occurs at the interface, and (3) contact between the fuel and cladding where the contact pressure is above a threshold value, such that axial slippage is prevented at the interface. The first stage of development of the model included only the fuel. In this stage, results obtained from the model were compared with those obtained from finite element analysis using ABAQUS on a problem involving elastic, plastic, and thermal strains. Results from the two analyses showed essentially exact agreement through both loading and unloading of the fuel. After the cladding and fuel/clad contact were added, the model demonstrated expected behavior through all potential phases of fuel/clad interaction, and convergence was achieved without difficulty in all plastic analysis performed. The code is currently in stand alone form. Prior to implementation into the TRU fuel performance code, creep strains will have to be added to the model. The model will also have to be verified against an ABAQUS analysis that involves contact between the fuel and cladding.« less
  • A survey is made of several types of fuel elements for an OMCR-type reactor. Square and hexagonal box snd circular tube configurations are considered. The fuel consists of U0/sub 2/ pins clad with finned tubing. The temperatures are limited to 850 deg F. Both forced convection and subcooled nucleate boiling effects are investigated. The hexagonal box fuel element is found to give performance superior to that of the other configurations. This type of element is optimized and its core performance characteristics are studied. (T.F.H.)
  • The Federal Mine Safety Code, Part 57 of the Federal Metal and Nonmetallic Mine Safety Act, was studied as to its effects upon the design and operation of that portion of the waste Isolation Pilot Plant pertaining to mining. These standards are discussed on a point by point basis.