Direct deterministic method for neutronics analysis and computation of asymptotic burnup distribution in a recirculating pebble-bed reactor

Terry, William S.; Gougar, Hans D.; Ougouag, Abderrafi M.

doi:10.1016/s0306-4549(01)00110-4

Cited by 59 publications

(20 citation statements)

References 7 publications

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“…Forward models include reactor physics codes tailored for specific reactor designs, such as PEBBED (Terry et al, 2002), which is intended for use with pebble bed reactors. These codes include empirical data and typically can compute with high accuracy a variety of operating parameters, including power production, refueling needs, and the spatial distribution of burn-up and principal nuclides throughout the reactor core and in the discharged fuels.…”

Section: On-line Refueled Reactor Examplementioning

confidence: 99%

Integration of facility modeling capabilities for nuclear nonproliferation analysis

García¹,

Burr²,

Coles³

et al. 2012

Progress in Nuclear Energy

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Developing automated methods for data collection and analysis that can facilitate nuclear nonproliferation assessment is an important research area with significant consequences for the effective global deployment of nuclear energy. Facility modeling that can integrate and interpret observations collected from monitored facilities in order to ascertain their functional details will be a critical element of these methods. Although improvements are continually sought, existing facility modeling tools can characterize all aspects of reactor operations and the majority of nuclear fuel cycle processing steps, and include algorithms for data processing and interpretation. Assessing nonproliferation status is challenging because observations can come from many sources, including local and remote sensors that monitor facility operations, as well as open sources that provide specific business information about the monitored facilities, and can be of many different types. Although many current facility models are capable of analyzing large amounts of information, they have not been integrated in an analyst-friendly manner. This paper addresses some of these facility modeling capabilities and illustrates how they could be integrated and utilized for nonproliferation analysis. The inverse problem of inferring facility conditions based on collected observations is described, along with a proposed architecture and computer framework for utilizing facility modeling tools. After considering a representative sampling of key facility modeling capabilities, the proposed integration framework is illustrated with several examples. Highlights: We consider integration of facility modeling into a tool for proliferation analysis.  We describe the inverse problem of inferring the facility based on observables.  We propose architecture for integrating facility models into a suitable framework.  We illustrate the proposed integration framework with several examples.

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Section: On-line Refueled Reactor Examplementioning

confidence: 99%

Integration of facility modeling capabilities for nuclear nonproliferation analysis

García¹,

Burr²,

Coles³

et al. 2012

Progress in Nuclear Energy

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show abstract

“…A code-to-code coupling between PEBBED [6] and SCALE-6 [7] has been implemented, which allows PEBBED to read microscopic neutron cross sections in AMPX format as generated with the CSAS5 module of SCALE-6. The fine (238) energy group structure from ENDF/B-VII is collapsed for this purpose to a broad group structure (12 groups, of which 7 are thermal) to be used in PEBBED.…”

Section: Code System For Analysis Of Pebble-bed Reactor Coresmentioning

confidence: 99%

“…The PEBBED code [6] is a tool for analyzing the asymptotic fuel cycle in recirculating pebble bed reactors. Equations for neutron flux and nuclide distribution in a pebble-bed core are solved selfconsistently via an iterative scheme.…”

Section: Description Of the Pebbed Codementioning

confidence: 99%

Final Report on Utilization of TRU TRISO Fuel as Applied to HTR Systems Part I: Pebble Bed Reactors

Boer¹,

Ougouag²

2011

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SUMMARYThe deep burn (DB) project aims at the destruction of legacy inventories of plutonium (Pu) and minor actinides (ma) leftover in used fuel from the operation of light water reactors (LWR). In its initial phase, the project examined the performance of high temperature reactors (HTR) for the db purpose. The performance is assessed based on two principal criteria. The first of these is "effectiveness," which pertains to the ability of the concept to indeed result in significant reduction of the Pu and MA inventories. The second criterion is "safety," which, for TRISO-based fuel, pertains primarily to the continuity of integrity of the TRISO particle, the primary barrier to the release of radionuclides from the fuel to the near field (i.e., within the reactor plant) and beyond (possibly to unrestricted public areas). Most of these issues have been addressed in previous reports. The focus of this final report is to present results on the optimization of the core of a db pebble bed reactor (PBR) and to examine the performance of the fuel in the variant of db that considers features akin to the modified open fuel cycle (MOFC) concept. In the context of this study, MOFC is represented by its implication of the inclusion of selected fission product isotopes and of some americium (am) content into the db fuel.

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“…A code-to-code coupling between PEBBED [4] and SCALE-6 [5] has been implemented, which allows PEBBED to read microscopic neutron cross sections in AMPX format generated with the CSAS5 module of SCALE-6. The fine (238) energy group structure from ENDF/B-VII is collapsed for this purpose to a broad group structure (12 groups, of which 7 are thermal) to be used in PEBBED.…”

Section: Code System For Analysis Of Pebble-bed Reactor Coresmentioning

confidence: 99%

Very High Temperature Reactor (VHTR) Deep Burn Core and Fuel Analysis -- Complete Design Selection for the Pebble Bed Reactor

Boer¹,

Ougouag²

2010

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Direct deterministic method for neutronics analysis and computation of asymptotic burnup distribution in a recirculating pebble-bed reactor

Cited by 59 publications

References 7 publications

Integration of facility modeling capabilities for nuclear nonproliferation analysis

Integration of facility modeling capabilities for nuclear nonproliferation analysis

Final Report on Utilization of TRU TRISO Fuel as Applied to HTR Systems Part I: Pebble Bed Reactors

Very High Temperature Reactor (VHTR) Deep Burn Core and Fuel Analysis -- Complete Design Selection for the Pebble Bed Reactor

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