Radionuclide Compositions and Total Activity of Spent MTR-HEU Fuel Elements of the IAN-R1 Research Reactor
Abstract
With cooperation of the International Atomic Energy Agency (IAEA) and the Department of Energy (DOE) of the United States, several calculations and tasks related to the waste disposal of spent MTR fuel enriched nominally to 93% were carried out for the conversion of the IAN-R1 Research Reactor from MTR-HEU fuel to TRIGA-LEU fuel. In order to remove the spent MTR-HEU fuel of the core and store it safely a program was established at the Instituto de Ciencias Nucleares y Energias Alternativas (INEA). This program included training, acquisition of hardware and software, design and construction of a decay pool, transfer of the spent HEU fuel elements into the decay pool and his final transport to Savannah River in United States. In this paper are presented data of activities calculated for each relevant radionuclide present in spent MTR-HEU fuel elements of the IAN-R1 Research Reactor and the total activity. The total activity calculated takes in consideration contributions of fission, activation and actinides products. The data obtained were the base for shielding calculations for the decay pool concerning the storage of spent MTR-HEU fuel elements and the respective dosimetric evaluations in the transferring operations of fuel elements into the decay pool.
- Authors:
-
- Distrital University Francisco Jose de Caldas, Cr 7 40-53, Bogota D.C. (Colombia)
- Publication Date:
- OSTI Identifier:
- 20722455
- Resource Type:
- Journal Article
- Journal Name:
- AIP Conference Proceedings
- Additional Journal Information:
- Journal Volume: 769; Journal Issue: 1; Conference: International conference on nuclear data for science and technology, Santa Fe, NM (United States), 26 Sep - 1 Oct 2004; Other Information: DOI: 10.1063/1.1945277; (c) 2005 American Institute of Physics; Country of input: International Atomic Energy Agency (IAEA); Journal ID: ISSN 0094-243X
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 73 NUCLEAR PHYSICS AND RADIATION PHYSICS; 12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; CONVERSION; DECAY; EVALUATION; FISSION; FUEL ELEMENTS; HIGHLY ENRICHED URANIUM; IAN; NUCLEAR FUELS; RADIOACTIVE WASTE DISPOSAL; REACTOR FUELING; RESEARCH REACTORS; SAVANNAH RIVER; SHIELDING
Citation Formats
Sarta, Jose A, and Castiblanco, Luis A. Radionuclide Compositions and Total Activity of Spent MTR-HEU Fuel Elements of the IAN-R1 Research Reactor. United States: N. p., 2005.
Web. doi:10.1063/1.1945277.
Sarta, Jose A, & Castiblanco, Luis A. Radionuclide Compositions and Total Activity of Spent MTR-HEU Fuel Elements of the IAN-R1 Research Reactor. United States. https://doi.org/10.1063/1.1945277
Sarta, Jose A, and Castiblanco, Luis A. 2005.
"Radionuclide Compositions and Total Activity of Spent MTR-HEU Fuel Elements of the IAN-R1 Research Reactor". United States. https://doi.org/10.1063/1.1945277.
@article{osti_20722455,
title = {Radionuclide Compositions and Total Activity of Spent MTR-HEU Fuel Elements of the IAN-R1 Research Reactor},
author = {Sarta, Jose A and Castiblanco, Luis A},
abstractNote = {With cooperation of the International Atomic Energy Agency (IAEA) and the Department of Energy (DOE) of the United States, several calculations and tasks related to the waste disposal of spent MTR fuel enriched nominally to 93% were carried out for the conversion of the IAN-R1 Research Reactor from MTR-HEU fuel to TRIGA-LEU fuel. In order to remove the spent MTR-HEU fuel of the core and store it safely a program was established at the Instituto de Ciencias Nucleares y Energias Alternativas (INEA). This program included training, acquisition of hardware and software, design and construction of a decay pool, transfer of the spent HEU fuel elements into the decay pool and his final transport to Savannah River in United States. In this paper are presented data of activities calculated for each relevant radionuclide present in spent MTR-HEU fuel elements of the IAN-R1 Research Reactor and the total activity. The total activity calculated takes in consideration contributions of fission, activation and actinides products. The data obtained were the base for shielding calculations for the decay pool concerning the storage of spent MTR-HEU fuel elements and the respective dosimetric evaluations in the transferring operations of fuel elements into the decay pool.},
doi = {10.1063/1.1945277},
url = {https://www.osti.gov/biblio/20722455},
journal = {AIP Conference Proceedings},
issn = {0094-243X},
number = 1,
volume = 769,
place = {United States},
year = {Tue May 24 00:00:00 EDT 2005},
month = {Tue May 24 00:00:00 EDT 2005}
}