Stochastic geometry capability in MCNP5 for the analysis of particle fuel

Brown, Forrest B.; Martin, William R.

doi:10.1016/j.anucene.2004.08.006

Cited by 53 publications

(9 citation statements)

References 8 publications

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“…The size of the graphite cell is determined by the packing fraction of the particle fuel. It has also been observed [13] that the predicted results are not very sensitive to the location of the microsphere within the graphite cell (i.e., random vs. centered), which provides some justification for assuming the microsphere is at the center of the cell. This is also an issue of input complexity and code capacity, since a fuel compact may have 6000 particles and it would be difficult to prepare an input file that described even a single compact, let alone a fuel block or full core.…”

Section: Background -Analysis Of Triso Particle Fuelmentioning

confidence: 89%

An Advanced Neutronic Analysis Toolkit with Inline Monte Carlo capability for BHTR Analysis

Martin¹,

Lee²

2009

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Section: Background -Analysis Of Triso Particle Fuelmentioning

confidence: 89%

An Advanced Neutronic Analysis Toolkit with Inline Monte Carlo capability for BHTR Analysis

Martin¹,

Lee²

2009

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“…(6) All-particle, all-energy Monte Carlo codes. 22) (7) Stochastic geometry 23) for modeling the random locations of fuel particles in newer reactor fuel systems. (8) Improved treatment of the free-gas scattering model at epithermal neutron energies 24) to include important resonance scattering effects.…”

Section: The Next Years Of Monte Carlo Codesmentioning

confidence: 99%

Recent Advances and Future Prospects for Monte Carlo

Brown

2011

Progress in Nuclear Science and Technology

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The history of Monte Carlo methods is closely linked to that of computers: The first known Monte Carlo program was written in 1947 for the ENIAC; a pre-release of the first Fortran compiler was used for Monte Carlo in 1957; Monte Carlo codes were adapted to vector computers in the 1980s, clusters and parallel computers in the 1990s, and teraflop systems in the 2000s. Recent advances include hierarchical parallelism, combining threaded calculations on multicore processors with message-passing among different nodes. With the advances in computing, Monte Carlo codes have evolved with new capabilities and new ways of use. Production codes such as MCNP, MVP, MONK, TRIPOLI, MCU, and KENO are now 20-30 years old (or more) and are very rich in advanced features. The former "method of last resort" has now become the first choice for many applications. Calculations are now routinely performed on office computers, not just on supercomputers. Current research and development efforts are investigating the use of Monte Carlo methods on FPGAs, GPUs, and many-core processors. Other far-reaching research is exploring ways to adapt Monte Carlo methods to future exaflop systems that may have 1M or more concurrent computational processes.

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“…Difilippo's model used structured, instead of random, particle distribution in the fuel pin and the TRISO particles were cut by the pebble fuel pin boundary. The impact of these two approximations has been studied in literature (Difilippo, 2006;Brown et al, 2005a,b;Brown and Martin, 2004;Colak and Seker, 2005) and the impact on the multiplication factor is about 200 pcm. In the QUADRISO particle concept, the absorber layer entirely covers the fuel kernel without any eventual cut by the pin boundary.…”

Section: Prismatic Htr Performance With Quadriso Particlesmentioning

confidence: 99%

A novel concept of QUADRISO particles. Part II: Utilization for excess reactivity control

Talamo

2010

Nuclear Engineering and Design

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In high temperature reactors, burnable absorbers are utilized to manage the excess reactivity at the early stage of the fuel cycle. In this paper QUADRISO particles are proposed to manage the initial excess reactivity of high temperature reactors. The QUADRISO concept synergistically couples the decrease of the burnable poison with the decrease of the fissile materials at the fuel particle level. This mechanism is set up by introducing a burnable poison layer around the fuel kernel in ordinary TRISO particles or by mixing the burnable poison with any of the TRISO coated layers. At the beginning of life, the initial excess reactivity is small because some neutrons are absorbed in the burnable poison and they are prevented from entering the fuel kernel. At the end of life, when the absorber is almost depleted, more neutrons stream into the fuel kernel of QUADRISO particles causing fission reactions. The mechanism has been applied to a prismatic high temperature reactor with europium or erbium burnable absorbers, showing a significant reduction in the initial excess reactivity of the core.

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Stochastic geometry capability in MCNP5 for the analysis of particle fuel

Cited by 53 publications

References 8 publications

An Advanced Neutronic Analysis Toolkit with Inline Monte Carlo capability for BHTR Analysis

An Advanced Neutronic Analysis Toolkit with Inline Monte Carlo capability for BHTR Analysis

Recent Advances and Future Prospects for Monte Carlo

A novel concept of QUADRISO particles. Part II: Utilization for excess reactivity control

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