MCNP and GADRAS Comparisons
- Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
To facilitate the timely execution of System Threat Reviews (STRs) for DNDO, and also to develop a methodology for performing STRs, LANL performed comparisons of several radiation transport codes (MCNP, GADRAS, and Gamma-Designer) that have been previously utilized to compute radiation signatures. While each of these codes has strengths, it is of paramount interest to determine the limitations of each of the respective codes and also to identify the most time efficient means by which to produce computational results, given the large number of parametric cases that are anticipated in performing STR's. These comparisons serve to identify regions of applicability for each code and provide estimates of uncertainty that may be anticipated. Furthermore, while performing these comparisons, examination of the sensitivity of the results to modeling assumptions was also examined. These investigations serve to enable the creation of the LANL methodology for performing STRs. Given the wide variety of radiation test sources, scenarios, and detectors, LANL calculated comparisons of the following parameters: decay data, multiplicity, device (n,γ) leakages, and radiation transport through representative scenes and shielding. This investigation was performed to understand potential limitations utilizing specific codes for different aspects of the STR challenges.
- Research Organization:
- Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA)
- DOE Contract Number:
- AC52-06NA25396
- OSTI ID:
- 1248125
- Report Number(s):
- LA-UR-16-22677; TRN: US1601259
- Country of Publication:
- United States
- Language:
- English
Similar Records
Simulation of Photon energy Spectra Using MISC, SOURCES, MCNP and GADRAS
FY2008 Report on GADRAS Radiation Transport Methods.
Related Subjects
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
M CODES
G CODES
COMPARATIVE EVALUATIONS
LANL
RADIATION TRANSPORT
NUCLEAR DECAY
DESIGN
NEUTRON LEAKAGE
MULTIPLICITY
SENSITIVITY ANALYSIS
SHIELDING
COMPUTERIZED SIMULATION
MULTIPLICATION FACTORS
URANIUM
PLUTONIUM
GAMMA RADIATION
STAINLESS STEELS