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Title: Requirements for GNEP Transmutation Fuels

Abstract

The purpose of this document is to provide a baseline set of requirements to guide fuel fabrication development and irradiation testing performed as part of the AFCRD Transmutation Fuel Development Program. This document can be considered a supplement to the GNEP TRU Fuel Development and Qualification Plan, and will be revised as necessary to maintain a documented set of fuel testing objectives and requirements consistent with programmatic decisions and advances in technical knowledge.

Authors:
; ;
Publication Date:
Research Org.:
Idaho National Laboratory (INL)
Sponsoring Org.:
DOE - NE
OSTI Identifier:
915526
Report Number(s):
INL/EXT-07-12468
TRN: US200817%%565
DOE Contract Number:
DE-AC07-99ID-13727
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
99 - GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE; FABRICATION; IRRADIATION; TESTING; TRANSMUTATION; FUELS; advanced fuel cycle; GNEP

Citation Formats

D. C. Crawford, M. K. Meyer, and S. L. Hayes. Requirements for GNEP Transmutation Fuels. United States: N. p., 2007. Web. doi:10.2172/915526.
D. C. Crawford, M. K. Meyer, & S. L. Hayes. Requirements for GNEP Transmutation Fuels. United States. doi:10.2172/915526.
D. C. Crawford, M. K. Meyer, and S. L. Hayes. Thu . "Requirements for GNEP Transmutation Fuels". United States. doi:10.2172/915526. https://www.osti.gov/servlets/purl/915526.
@article{osti_915526,
title = {Requirements for GNEP Transmutation Fuels},
author = {D. C. Crawford and M. K. Meyer and S. L. Hayes},
abstractNote = {The purpose of this document is to provide a baseline set of requirements to guide fuel fabrication development and irradiation testing performed as part of the AFCRD Transmutation Fuel Development Program. This document can be considered a supplement to the GNEP TRU Fuel Development and Qualification Plan, and will be revised as necessary to maintain a documented set of fuel testing objectives and requirements consistent with programmatic decisions and advances in technical knowledge.},
doi = {10.2172/915526},
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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  • The possibilities of several new technologies based on use of intense, medium-energy proton accelerators are being investigated at Los Alamos National Laboratory. The potential new areas include destruction of long-lived components of nuclear waste, plutonium burning, energy production, and production of tritium. The design, assessment, and safety analysis of potential facilities involves the understanding of complex combinations of nuclear processes, which in turn places new requirements on nuclear data that transcend the traditional needs of the fission and fusion reactor communities. In this paper an assessment of the nuclear data needs for systems currently being considered in the Los Alamosmore » Accelerator-Driven Transmutation Technologies program is given. The importance of developing neutron and proton cross section libraries in the incident particle energy range of 20 MeV to approximately 200 MeV for transport applications is discussed, and new theoretical methods for developing cross section libraries at higher incident neutron and proton energies are summarized.« less
  • The U.S. Advanced Fuel Cycle Initiative (AFCI), now within the broader context of the Global Nuclear Energy Partnership (GNEP), seeks to develop and demonstrate the technologies needed to transmute the long-lived transuranic actinide isotopes contained in spent nuclear fuel into shorter-lived fission products, thereby dramatically decreasing the volume of material requiring disposal and the long-term radio-toxicity and heat load of high-level waste sent to a geologic repository. One important component of the technology development is actinide-bearing metallic transmutation fuel forms containing plutonium, neptunium, americium (and possibly curium) isotopes. The proposed AFC-2A and AFC-2B irradiation experiments are a continuation of themore » metallic fuel test series in progress in the ATR. This report documents the experiment description and test matrix of the proposed experiments and the Post Irradiation Examination (PIE) and fabrication schedule.« less
  • The AFC-1B, AFC-1F and AFC-1Æ irradiation tests are part of a series of test irradiations designed to evaluate the feasibility of the use of actinide bearing fuel forms in advanced fuel cycles for the transmutation of transuranic elements from nuclear waste. The tests were irradiated in the Idaho National Laboratory’s (INL) Advanced Test Reactor (ATR) to an intermediate burnup of 4 to 8 at% (2.7 - 6.8 x 1020 fiss/cm3). The tests contain metallic and nitride fuel forms with non-fertile (i.e., no uranium) and low-fertile (i.e., uranium bearing) compositions. Results of postirradiation hot cell examinations of AFC-1 irradiation tests aremore » reported for eleven metallic alloy transmutation fuel rodlets and five nitride transmutation fuel rodlets. Non-destructive examinations included visual examination, dimensional inspection, gamma scan analysis, and neutron radiography. Detailed examinations, including fission gas puncture and analysis, metallography / ceramography and isotopics and burnup analyses, were performed on five metallic alloy and three nitride transmutation fuels. Fuel performance of both metallic alloy and nitride fuel forms was best correlated with fission density as a burnup metric rather than at.% depletion. The actinide bearing transmutation metallic alloy compositions exhibit irradiation performance very similar to U-xPu-10Zr fuel at equivalent fission densities. The irradiation performance of nitride transmutation fuels was comparable to limited data published on mixed nitride systems.« less
  • The U.S. Advanced Fuel Cycle Initiative (AFCI), now within the broader context of the Global Nuclear Energy Partnership (GNEP), seeks to develop and demonstrate the technologies needed to transmute the long-lived transuranic actinide isotopes contained in spent nuclear fuel into shorter-lived fission products, thereby dramatically decreasing the volume of material requiring disposal and the long-term radio-toxicity and heat load of high-level waste sent to a geologic repository. One important component of the technology development is actinide-bearing metallic transmutation fuel forms containing plutonium, neptunium, americium (and possibly curium) isotopes. The proposed AFC-2A and AFC-2B irradiation experiments are a continuation of themore » metallic fuel test series in progress in the ATR. This report documents the experiment description and test matrix of the proposed experiments and the Post Irradiation Examination (PIE) and fabrication schedule.« less
  • The U.S. Advanced Fuel Cycle Initiative (AFCI), now within the broader context of the Global Nuclear Energy Partnership (GNEP), seeks to develop and demonstrate the technologies needed to transmute the long-lived transuranic actinide isotopes contained in spent nuclear fuel into shorter-lived fission products, thereby dramatically decreasing the volume of material requiring disposal and the long-term radio-toxicity and heat load of high-level waste sent to a geologic repository. One important component of the technology development is actinide-bearing metallic transmutation fuel forms containing plutonium, neptunium, americium (and possibly curium) isotopes. The proposed AFC-2A and AFC-2B irradiation experiments are a continuation of themore » metallic fuel test series in progress in the ATR. This report documents the experiment description and test matrix of the proposed experiments and the Post Irradiation Examination (PIE) and fabrication schedule.« less