A New Monte Carlo Tallying Methodology for Optimizing the Nuclear Energy Research Initiative Spherical-Shell Transmission Experiment
The development of a new tallying methodology for use with the MCNP Monte Carlo particle transport code is reported. The objective is to be able to determine with accuracy the iron nonelastic scattering cross sections via a spherical-shell transmission experiment using the time-of-flight (TOF) method. Different source energy and shell thickness combinations are examined. The actual transmission experiment and the new tallying algorithm are described, and the verification of the new tallying algorithm and its utilization to optimize a neutron TOF experiment are discussed. The results of the work will be used to alleviate the well-known deficiency that exists in the iron nonelastic scattering cross section and thereby reduce the uncertainty in calculations involving deep penetration in iron, e.g. reactor pressure vessel neutron fluence determinations.
- Research Organization:
- The Pennsylvania State University, University Park, Pennsylvania (US); National Institute of Standards and Technology, Gaithersburg, Maryland (US); Ohio University, Athens, Ohio (US)
- Sponsoring Organization:
- US Department of Energy (US)
- OSTI ID:
- 786229
- Report Number(s):
- ISSN 0003-018X; CODEN TANSAO; ISSN 0003-018X; CODEN TANSAO; TRN: US0108841
- Resource Relation:
- Conference: 2001 Annual Meeting, Milwaukee, WI (US), 06/17/2001--06/21/2001; Other Information: Transactions of the American Nuclear Society, volume 84; PBD: 17 Jun 2001
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
ACCURACY
ALGORITHMS
CROSS SECTIONS
IRON
NEUTRON FLUENCE
NEUTRON TRANSPORT
PRESSURE VESSELS
VERIFICATION
MONTE CARLO METHOD
NEUTRON TRANSPORT THEORY
M CODES
FAST NEUTRONS
MEV RANGE 01-10