MOX and MOX with 237Np/241Am Inert Fission Gas Generation Comparison in ATR
Abstract
The treatment of spent fuel produced in nuclear power generation is one of the most important issues to both the nuclear community and the general public. One of the viable options to long-term geological disposal of spent fuel is to extract plutonium, minor actinides (MA), and potentially long-lived fission products from the spent fuel and transmute them into short-lived or stable radionuclides in currently operating light-water reactors (LWR), thus reducing the radiological toxicity of the nuclear waste stream. One of the challenges is to demonstrate that the burnup-dependent characteristic differences between Reactor-Grade Mixed Oxide (RG-MOX) fuel and RG-MOX fuel with MA Np-237 and Am 241 are minimal, particularly, the inert gas generation rate, such that the commercial MOX fuel experience base is applicable. Under the Advanced Fuel Cycle Initiative (AFCI), developmental fuel specimens in experimental assembly LWR-2 are being tested in the northwest (NW) I-24 irradiation position of the Advanced Test Reactor (ATR). The experiment uses MOX fuel test hardware, and contains capsules with MOX fuel consisting of mixed oxide manufactured fuel using reactor grade plutonium (RG-Pu) and mixed oxide manufactured fuel using RG-Pu with added Np/Am. This study will compare the fuel neutronics depletion characteristics of Case-1 RG-MOX andmore »
- Authors:
- Publication Date:
- Research Org.:
- Idaho National Lab. (INL), Idaho Falls, ID (United States)
- Sponsoring Org.:
- DOE - NE
- OSTI Identifier:
- 911576
- Report Number(s):
- INL/CON-06-01097
TRN: US0800017
- DOE Contract Number:
- DE-AC07-99ID-13727
- Resource Type:
- Conference
- Resource Relation:
- Conference: ANS Annual Meeting,Reno, NV,06/04/2006,06/08/2006
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 11 - NUCLEAR FUEL CYCLE AND FUEL MATERIALS; ACTINIDES; FISSION; FISSION PRODUCTS; FUEL CYCLE; IRRADIATION; NUCLEAR POWER; OXIDES; PLUTONIUM; RADIOACTIVE WASTES; RADIOISOTOPES; SPENT FUELS; TEST REACTORS; TOXICITY; fuel; light-water reactors; spent fuel treatment
Citation Formats
Chang, G S, Robel, M, Carmack, W J, and Utterbeck, D J. MOX and MOX with 237Np/241Am Inert Fission Gas Generation Comparison in ATR. United States: N. p., 2006.
Web.
Chang, G S, Robel, M, Carmack, W J, & Utterbeck, D J. MOX and MOX with 237Np/241Am Inert Fission Gas Generation Comparison in ATR. United States.
Chang, G S, Robel, M, Carmack, W J, and Utterbeck, D J. 2006.
"MOX and MOX with 237Np/241Am Inert Fission Gas Generation Comparison in ATR". United States. https://www.osti.gov/servlets/purl/911576.
@article{osti_911576,
title = {MOX and MOX with 237Np/241Am Inert Fission Gas Generation Comparison in ATR},
author = {Chang, G S and Robel, M and Carmack, W J and Utterbeck, D J},
abstractNote = {The treatment of spent fuel produced in nuclear power generation is one of the most important issues to both the nuclear community and the general public. One of the viable options to long-term geological disposal of spent fuel is to extract plutonium, minor actinides (MA), and potentially long-lived fission products from the spent fuel and transmute them into short-lived or stable radionuclides in currently operating light-water reactors (LWR), thus reducing the radiological toxicity of the nuclear waste stream. One of the challenges is to demonstrate that the burnup-dependent characteristic differences between Reactor-Grade Mixed Oxide (RG-MOX) fuel and RG-MOX fuel with MA Np-237 and Am 241 are minimal, particularly, the inert gas generation rate, such that the commercial MOX fuel experience base is applicable. Under the Advanced Fuel Cycle Initiative (AFCI), developmental fuel specimens in experimental assembly LWR-2 are being tested in the northwest (NW) I-24 irradiation position of the Advanced Test Reactor (ATR). The experiment uses MOX fuel test hardware, and contains capsules with MOX fuel consisting of mixed oxide manufactured fuel using reactor grade plutonium (RG-Pu) and mixed oxide manufactured fuel using RG-Pu with added Np/Am. This study will compare the fuel neutronics depletion characteristics of Case-1 RG-MOX and Case-2 RG-MOX with Np/Am.},
doi = {},
url = {https://www.osti.gov/biblio/911576},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu Jun 01 00:00:00 EDT 2006},
month = {Thu Jun 01 00:00:00 EDT 2006}
}