MCNP-PoliMi: A Monte-Carlo code for correlation measurements

Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment

Volumn 513, Issue 3, 2003, Pages 550-558

  Pozzi, Sara A ^a   Padovani, Enrico ^a   Marseguerra, Marzio ^a  

^a POLITECNICO DI MILANO   (Italy)

Author keywords

Correlation measurement; MCNP; MCNP PoliMi; Nuclear safeguards; Plastic scintillation detector

Indexed keywords

COMPUTER SIMULATION; FISSION REACTIONS; MONTE CARLO METHODS; PHOTONS; SCINTILLATION;

PARTICLE INTERACTIONS;

NEUTRONS;

EID: 0142248223     PISSN: 01689002     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nima.2003.06.012     Document Type: Article

References (11)

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2. J.F. Briesmeister (Ed). MCNP - A General Monte Carlo N-Particle Transport Code, Version 4C, LA-13709-M, Los Alamos National Laboratory, April 2000.
3. M. Marseguerra, E. Padovani, S.A. Pozzi, Simulating the wrong physics can yield correct results, 3rd IMACS Seminar on Monte Carlo Methods MCM2001, September 10-14, 2001, Salzburg, Austria.
4. T.E. Valentine, MCNP-DSP Users Manual, ORNL/TM-13334, Oak Ridge National Laboratory, 1997.
5. Abhold M.E., Baker M.C. Nucl. Instr. and Meth. A. 485:2002;576.
6. E. Padovani, S.A. Pozzi, MCNP-PoliMi ver.1.0 user's manual, CESNEF-021125, Library of Nuclear Engineering Department, Politecnico di Milano, November 2002.
7. Valentine T.E. Ann. Nucl. Energy. 28:2001;191.
8. S.A. Pozzi, J.T. Mihalczo, Monte Carlo Evaluation of the Improvements in Nuclear Materials Identification System (NMIS) resulting from a DT Neutron Generator, Institute of Nuclear Materials Management 43rd Annual Meeting, June 23-27, 2002, Orlando, FL, USA.
9. M. Marseguerra, E. Padovani, S.A. Pozzi, Phenomenological simulation of detector response for safeguards experiments, IRRMA-V, 5th International Topical Meeting on Industrial Radiation and Radioisotope Measurement Applications, Bologna, Italy, 9-14 June 2002.
10. S.A. Pozzi, J.K. Mattingly, J.T. Mihalczo, E. Padovani, Validation of the Monte Carlo code MCNP-PoliMi. Part I: Plutonium, Oak Ridge Y-12 Plant, Y/LB-16,138, 2002.
11. S.A. Pozzi, J.K. Mattingly, J.T. Mihalczo, E. Padovani, Validation of the MCNP-PoliMi Code for the Simulation of Nuclear Safeguards Experiments on Uranium and Plutonium Metal, Nuclear Mathematical and Computational Sciences: A Century in Review, a Century Anew, Gatlinburg, Tennessee, April 6-11, 2003, on CD-ROM, American Nuclear Society, LaGrange Park, IL, 2003.