Fast-Mixed Spectrum Reactor Interim Report Initial Feasibility Study.

Fischer, G.J.; Cerbone, R.J.

doi:10.2172/12067642

Cited by 8 publications

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“…The metal fuel and materials aspects of the (EC)FMSR design are not discussed in this report. These have been described to some degree in two previous reports* 1 ' 6 ' and will not be repeated here. An advantage of the (EC)FMSR design is that the anticipated peak fuel burnup can now be made significantly less than that required for the (CM)FHSR and close to that which has already been achieved with about 1000 metal fuel pins in EBR-II.…”

Section: Uranium Resource Requirementsmentioning

confidence: 58%

Fast-mixed spectrum reactor. Progress report for 1980

Fischer¹,

Galperin²,

Shenoy³

et al. 1980

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2.1 INTRODUCTION , 3 2.2 CELL BURNUP CALCULATIONS 4 2.3 AIMS OF THE PRESENT STUDY 6 2.4 (CM)FMSR DESIGN AND CALCULATIONS 8 2.4.1 Reactor Configuration 8 2.4.2 Startup Core Calculations 10 2.4.3 Fuel Management Strategy 14 2.4.4 Results of Burnup Calculations 20 2.4.5 Reactivity Coefficients 24 2.4.6 Reactor Control During Burnup Cycles. ........ 29 2.4.7 Thermal-Hydraulic Calculations 29 2.5 URANIUM RESOURCE REQUIREMENTS 31 3. THE EXTENDED FUEL CYCLE FMSR [(EC)FMSR] CONCEPT-PHYSICS ANALYSIS 33 3.1 INTRODUCTION 33 3.2 (EC)FMSR DESIGN CONSIDERATIONS «. 36 3.3 CALCULATION METHODS 39 3.3.1 Cross-Section Generation 39 3.3.2 Hexagonal and R-Z Models of the (EC)FHSR Core .... 44 3.4 RESULTS OF THE (EC)FMSR PHYSICS ANALYSES 49 3.4.1 Reactivity Swing and Plutonium Concentrations During the Fuel Cycle 49 iii-TABLE OF CONTENTS (cont'd) Page 3.4.2 Power Shape anu Power Swing. 51 3.4.3 Burnup and Fast Fluence Damage 55 3.4.4 Reactivity Coefficients 55 3.4.5 Radial and Axial Blankets 64 3.4.6 Reactivity Control Systems 64 4. THERMAL-HYDRAULIC ANALYSIS OF THE (EC)FMSR 78 4.1 GENERAL DESIGN CONSIDERATIONS ... 78 4.2 METHOD OF CALCULATION 78 4.3 THERMAL-HYDRAULIC PERFORMANCE 79 5. (EC)FMSR FUEL CYCLE COST ANALYSIS 83 5.1 INTRODUCTION. 83 5.2 FUEL CYCLE COST MODEL AND THE ECONOMIC ENVIRONMENT 83 5.3 RESULTS AND CONCLUSIONS 88 6. THE 30-YEAR (EC)FMSR 94 6,1 PRELIMINARY RESULTS OF THE 30-YEAR (EC)FMSR 94 7. CONCLUSIONS AND RECOMMENDATIONS 102 7.1 CONCLUSIONS 102 7.2 RECOMMENDATIONS 103 LIST OF TABLES (cont'd) Table Page 3.16 Control Rod Reactivity Worths 72 4.1 Summary of Core Fuel Thermal Hydraulics for the (EC)FMSR.. 80 4.2 Thermal-Hydraulic Results for Average Pin at Nominal Conditions in Zone 1 of (EC)FMSR 82 4.3 Thermal-Hydraulic Results for the Hot Pin in Zone 1 of the (EC)FMSR 84 5.1 Unit Cost and Financial Parameters Used in the Fuel Cycle Cost Calculations 86 5.2 Unit Cost of Fissile Plutonium Based on the Recovery Costs from PWR Spent Fuel 87 5.3 Cash Flow Associated with Core and Blanket Fuel Assemblies of (EC)FMSR 89 5.4 Cash Flow Associated with Core and Blanket Fuel Assemblies of a Homogeneous LMFBR (1200 MW(e)) 91 5.5 Cash Flow Associated with Core and Blanket Fuel Assemblies of a Heterogeneous LMFBR (1000 HW(e) Core) 92 5.6 Comparison Between the Levelized Fuel Cycle Cost of the (EC)FHSR and a Homogeneous and Heterogeneous LMFBR 93 6.1 Comparison Between 10-and 30-Year (EC)FMSR Cores 95 6.2 30-Year FMSR Performance 98 6.3 Cash Flow Associated with Core and Blanket Fuel Assemblies of the 30-Year FMSR 99 6.4 Comparison Between the Levelized Fuel Cycle Cost of the 10and 20-Year FMSR and a Heterogeneous LMFBR 100 6.5 Advantages and Disadvantages of the 30-Year FMSR Design. . 100-vi-LIST OF FIGURES Figure Page 2.1 Variation of K e ff and Breeding Ratio with Peak Cell Burnup , 7 2.2 Schematic View of the Centrally-Moderated FMSR in the X-Y Plane 9 2.3 Reactor Layout in the X-Y Plane for the (CM)FMSR 12 2.4 Schematic R-Z Representation of the (CM)FMSR 13 2.5 Neutron Energy Spectra at the Beginning)f Reactor Life for the (CM...

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Section: Uranium Resource Requirementsmentioning

confidence: 58%

Fast-mixed spectrum reactor. Progress report for 1980

Fischer¹,

Galperin²,

Shenoy³

et al. 1980

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“…In 1979 and 1980, a new concept was studied. This concept called the fast mixed spectrum reactor consists in a core with both fast and thermal zones: fertile and fissile materials are placed in these zones, and after a certain time new fissile fuel bred in the fertile areas are placed in the fissile zones.…”

Section: Brief Chronology Of the Breed/burn Reactor Concept Developmentmentioning

confidence: 99%

“…The fast mixed spectrum reactor (FMSR) concept was developed by the Brookhaven National Laboratory (BNL) with the aim of proliferation resistance and good uranium utilization . The key feature is the use of a once‐through fuel cycle without need of fuel reprocessing, because after the first cycle, the new fuel added to the core can be natural or depleted fuel.…”

Section: Types Of Breed/burn Reactor Coresmentioning

confidence: 99%

The breed and burn nuclear reactor: A chronological, conceptual, and technological review

Lopez-Solis

François

2017

Int J Energy Res

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Summary Currently about 11% of the world's energy is produced in nuclear power plants; this implies the processing of uranium in order to enrich it to be suitable for “burning” in a nuclear reactor. Besides other environmental and monetary costs involved in the whole nuclear fuel cycle, the enrichment process has the disadvantage of producing depleted uranium as a sub‐product that has no wide use and is essentially stockpiled. One strategy to deal with this issue is to design a nuclear reactor that can run mostly on depleted uranium by breeding its own fissile fuel from it. Even though this concept could sound innovative or new, the truth is that it has been in the thought of the nuclear engineers since the 50s. In the present paper, the breed & burn (B&B) reactor concept is reviewed, as well as its origins, evolution up to present, and its main technical features. The objectives of this review are as follows: (1) to summarize the history of the development of B&B reactors, (2) to compare different B&B concepts based on a systematic approach under selected technical features, and (3) to bring out current trends and future directions on this technology. It is expected that this review will help the nuclear engineering community in general, and newcomer researchers in the field, to get an overview about the B&B reactors and how to direct a research in this direction.

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“…Today the European Commission is advancing the goal of access to open data in a transparent way. This goal has prompted several initiatives such as INSPIRE [4], EMODnet [5], SeaDataNet [6], JericoNEXT [7] and AtlantOS [8]. These initiatives subsequently advance a complimentary international goal of interoperable and open ocean data.…”

Section: Introductionmentioning

confidence: 99%

Interoperable Ocean Observing using Archetypes: A use-case based evaluation

Stacey¹,

Berry²

2018

OCEANS 2018 MTS/IEEE Charleston

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This paper presents a use-case based evaluation of the impact of two-level modeling on the automatic federation of ocean observational data. The goal of the work is to increase the interoperability and data quality of aggregated ocean observations to support convenient discovery and consumption by applications. An assessment of the interoperability of served data flows from publicly available ocean observing spatial data infrastructures was performed. Barriers to consumption of existing standardscompliant ocean-observing data streams were examined, including the impact of adherence to agreed data standards. Historical data flows were mapped to a set of archetypes and a backward integration experiment was performed to assess the incremental benefit of using two level models to federate data streams. The outcome of the evaluation demonstrates the feasibility of building a two-level model based ocean observing system using a combination of existing open source components, the adaptation of existing standards and the development of new software tools. The automatic integration of data flows becomes possible. This technique also allows real-time applications to automatically discover and federate newly discovered data flows and observations.

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Fast-Mixed Spectrum Reactor Interim Report Initial Feasibility Study.

Cited by 8 publications

References 0 publications

Fast-mixed spectrum reactor. Progress report for 1980

Fast-mixed spectrum reactor. Progress report for 1980

The breed and burn nuclear reactor: A chronological, conceptual, and technological review

Interoperable Ocean Observing using Archetypes: A use-case based evaluation

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