MCNP capabilities at the dawn of the 21st century: Neutron-gamma applications
- and others
The Los Alamos National Laboratory Monte Carlo N-Particle radiation transport code, MCNP, has become an international standard for a wide spectrum of neutron-gamma radiation transport applications. These include nuclear criticality safety, radiation shielding, nuclear safeguards, nuclear well-logging, fission and fusion reactor design, accelerator target design, detector design and analysis, health physics, medical radiation therapy and imaging, radiography, decontamination and decommissioning, and waste storage and disposal. The latest version of the code, MCNP4C, was released to the Radiation Safety Information Computational Center (RSICC) in February 2000.This paper described the new features and capabilities of the code, and discusses the specific applicability to neutron-gamma problems. We will also discuss the future directions for MCNP code development, including rewriting the code in Fortran 90.
- Research Organization:
- Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
- Sponsoring Organization:
- US Department of Energy (US)
- DOE Contract Number:
- W-7405-ENG-36
- OSTI ID:
- 765580
- Report Number(s):
- LA-UR-00-5017; TRN: US0100919
- Resource Relation:
- Conference: MC2000 Monte Carlo 2000 Advanced Monte Carlo for Radiation Physics, Particle Transport Simulation, and Applications, Lisbon (PT), 10/23/2000--10/26/2000; Other Information: PBD: 1 Oct 2000
- Country of Publication:
- United States
- Language:
- English
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