Status of Monte Carlo at Los Alamos

Thompson, William L.; Cashwell, E.D.

doi:10.2172/5361246

Cited by 7 publications

(5 citation statements)

References 3 publications

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“…In 1977, MCN and other Los Alamos Monte Carlo transport codes were merged together and named MCNP. 75 At first MCNP stood for Monte Carlo Neutron Photon. Today it stands for the Monte Carlo N−Particle® code since high-energy physics particles are now available.…”

Section: Ivd Los Alamos Monte Carlo Code Development Historymentioning

confidence: 99%

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Neutronics Calculation Advances at Los Alamos: Manhattan Project to Monte Carlo

et al. 2021

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The history and advances of neutronics calculations at Los Alamos during the Manhattan Project through the present is reviewed. We briefly summarize early simpler, and more approximate neutronics methods. We then motivate the need to better predict neutronics behavior through consideration of theoretical equations, models and algorithms, experimental measurements, and available computing capabilities and their limitations. These, coupled with increasing post-war defense needs, and the invention of electronic computing led to the creation of Monte Carlo neutronics transport. As a part of the history, we note the crucial role that the scientific comradery between the great Los Alamos scientists played in the process. We focus heavily on these early developments and the subsequent successes of Monte Carlo and its applications to problems of national defense at Los Alamos. We cover the early methods, algorithms, and computers, electronic and women pioneers, that enabled Monte Carlo to spread to all areas of science.

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Section: Ivd Los Alamos Monte Carlo Code Development Historymentioning

confidence: 99%

“…Finally, in 1980 when the MCNP® code was under early development, a new report on the status of Monte Carlo at Los Alamos asserted that "MCNP is a continuous-energy Monte Carlo code that makes no gross assumptions regarding data." 83…”

Section: Ive1 Theme For the Past 65 Years-nuclear Data Is Important A...mentioning

confidence: 99%

Neutronics Calculation Advances at Los Alamos: Manhattan Project to Monte Carlo

et al. 2021

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“…Since it was apparent that MCS and MCVMG results were bracketed in all cases by other results, these calculations were not continued to small statistical error, and the relatively large error bars for MCS and MCVMG reflect this. Additional results from Thompson et al (1980) not shown on Fig. 9 are the 240 group calculations performed using MCNP in a pseudo-multigroup fashion.…”

Section: Multigroup Analysis Of Deep-penetration Qfmentioning

confidence: 99%

Monte Carlo methods for radiation transport analysis on vector computers

Brown

Martin

1984

Progress in Nuclear Energy

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The development of advanced computers with special capabilities for vectorized or parallel calculations demands the development of new calculational methods. The very nature of the Monte Carlo process precludes direct conversion of old (scalar) codes to the new machines. Instead, major changes in global algorithms and careful selection of compatible physics treatments are required. Recent results for Monte Carlo in multigroup shielding applications and in continuous-energy reactor lattice analysis have demonstrated that Monte Carlo methods can be successfully vectorized. The significant effort required for stylized coding and major algorithmic changes is worthwhile, and significant gains in computational efficiency are realized. Speedups of at least twenty to forty times faster than CDC-7600 scalar calculations have been achieved on the CYBER-205 without sacrificing the accuracy of standard Monte Carlo methods. Speedups of this magnitude provide reductions in statistical uncertainties for a given amount of computing time, permit more detailed and realistic problems to be analyzed, and make the Monte Carlo method more accessible to nuclear analysts. Following overviews of the Monte Carlo method for particle transport analysis and of vector computer hardware and software characteristics, both general and specific aspects of the vectorization of Monte Carlo are discussed. Finally, numerical results obtained from vectorized Monte Carlo codes run on the CYBER-205 are presented.

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“…The particle simulation code MCNP is widely used to compute neutron, photon, electron and their coupling transport problem in complicating three dimensional geometries [1]. The basic of parallel version of MCNP or other Monte Carlo simulation is generating high quality, long period random numbers as quickly as possible [2].…”

Section: Introductionmentioning

confidence: 99%

Accelerating Pseudo-Random Number Generator for MCNP on GPU

Gong¹,

Liu²,

Chi³

et al. 2010

AIP Conference Proceedings

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Pseudo-random number generators (PRNG) are intensively used in many stochastic algorithms in particle simulations, artificial neural networks and other scientific computation. The PRNG in Monte Carlo N-Particle Transport Code (MCNP) requires long period, high quality, flexible jump and fast enough. In this paper, we implement such a PRNG for MCNP on NVIDIA's GTX200 Graphics Processor Units (GPU) using CUDA programming model. Results shows that 3.80 to 8.10 times speedup are achieved compared with 4 to 6 cores CPUs and more than 679.18 million double precision random numbers can be generated per second on GPU.

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Status of Monte Carlo at Los Alamos

Cited by 7 publications

References 3 publications

Neutronics Calculation Advances at Los Alamos: Manhattan Project to Monte Carlo

Neutronics Calculation Advances at Los Alamos: Manhattan Project to Monte Carlo

Monte Carlo methods for radiation transport analysis on vector computers

Accelerating Pseudo-Random Number Generator for MCNP on GPU

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