skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Advanced Safeguards Approaches for New Fast Reactors

Abstract

This third report in the series reviews possible safeguards approaches for new fast reactors in general, and the ABR in particular. Fast-neutron spectrum reactors have been used since the early 1960s on an experimental and developmental level, generally with fertile blanket fuels to “breed” nuclear fuel such as plutonium. Whether the reactor is designed to breed plutonium, or transmute and “burn” actinides depends mainly on the design of the reactor neutron reflector and the whether the blanket fuel is “fertile” or suitable for transmutation. However, the safeguards issues are very similar, since they pertain mainly to the receipt, shipment and storage of fresh and spent plutonium and actinide-bearing “TRU”-fuel. For these reasons, the design of existing fast reactors and details concerning how they have been safeguarded were studied in developing advanced safeguards approaches for the new fast reactors. In this regard, the design of the Experimental Breeder Reactor-II “EBR-II” at the Idaho National Laboratory (INL) was of interest, because it was designed as a collocated fast reactor with a pyrometallurgical reprocessing and fuel fabrication line – a design option being considered for the ABR. Similarly, the design of the Fast Flux Facility (FFTF) on the Hanford Site was studied, becausemore » it was a successful prototype fast reactor that ran for two decades to evaluate fuels and the design for commercial-scale fast reactors.« less

Authors:
; ; ; ; ; ; ; ;
Publication Date:
Research Org.:
Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
949148
Report Number(s):
PNNL-17168
NN4003010; TRN: US0901889
DOE Contract Number:  
AC05-76RL01830
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; ACTINIDES; DESIGN; FABRICATION; FAST REACTORS; IDAHO; NEUTRON REFLECTORS; NUCLEAR FUELS; PLUTONIUM; REPROCESSING; SAFEGUARDS; STORAGE; TRANSMUTATION; advanced safeguards; fast reactors; ABR; Monju

Citation Formats

Durst, Philip C., Therios, Ike, Bean, Robert, Dougan, A., Boyer, Brian, Wallace, Rick L., Ehinger, Michael H., Kovacic, Don N., and Tolk, K. Advanced Safeguards Approaches for New Fast Reactors. United States: N. p., 2007. Web. doi:10.2172/949148.
Durst, Philip C., Therios, Ike, Bean, Robert, Dougan, A., Boyer, Brian, Wallace, Rick L., Ehinger, Michael H., Kovacic, Don N., & Tolk, K. Advanced Safeguards Approaches for New Fast Reactors. United States. doi:10.2172/949148.
Durst, Philip C., Therios, Ike, Bean, Robert, Dougan, A., Boyer, Brian, Wallace, Rick L., Ehinger, Michael H., Kovacic, Don N., and Tolk, K. Sat . "Advanced Safeguards Approaches for New Fast Reactors". United States. doi:10.2172/949148. https://www.osti.gov/servlets/purl/949148.
@article{osti_949148,
title = {Advanced Safeguards Approaches for New Fast Reactors},
author = {Durst, Philip C. and Therios, Ike and Bean, Robert and Dougan, A. and Boyer, Brian and Wallace, Rick L. and Ehinger, Michael H. and Kovacic, Don N. and Tolk, K.},
abstractNote = {This third report in the series reviews possible safeguards approaches for new fast reactors in general, and the ABR in particular. Fast-neutron spectrum reactors have been used since the early 1960s on an experimental and developmental level, generally with fertile blanket fuels to “breed” nuclear fuel such as plutonium. Whether the reactor is designed to breed plutonium, or transmute and “burn” actinides depends mainly on the design of the reactor neutron reflector and the whether the blanket fuel is “fertile” or suitable for transmutation. However, the safeguards issues are very similar, since they pertain mainly to the receipt, shipment and storage of fresh and spent plutonium and actinide-bearing “TRU”-fuel. For these reasons, the design of existing fast reactors and details concerning how they have been safeguarded were studied in developing advanced safeguards approaches for the new fast reactors. In this regard, the design of the Experimental Breeder Reactor-II “EBR-II” at the Idaho National Laboratory (INL) was of interest, because it was designed as a collocated fast reactor with a pyrometallurgical reprocessing and fuel fabrication line – a design option being considered for the ABR. Similarly, the design of the Fast Flux Facility (FFTF) on the Hanford Site was studied, because it was a successful prototype fast reactor that ran for two decades to evaluate fuels and the design for commercial-scale fast reactors.},
doi = {10.2172/949148},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2007},
month = {12}
}

Technical Report:

Save / Share: