Validation of the MCNP-DSP Monte Carlo code for calculating source-driven noise parameters of subcritical systems
Journal Article
·
· Transactions of the American Nuclear Society
OSTI ID:186553
- Oak Ridge National Lab., TN (United States)
This paper describes calculations performed to validate the modified version of the MCNP code, the MCNP-DSP, used for: the neutron and photon spectra of the spontaneous fission of californium 252; the representation of the detection processes for scattering detectors; the timing of the detection process; and the calculation of the frequency analysis parameters for the MCNP-DSP code.
- OSTI ID:
- 186553
- Report Number(s):
- CONF-950601--
- Journal Information:
- Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 72; ISSN 0003-018X; ISSN TANSAO
- Country of Publication:
- United States
- Language:
- English
Similar Records
The MCNP-DSP code for calculations of time and frequency analysis parameters for subcritical systems
Coupling MCNP-DSP and LAHET Monte Carlo Codes for Designing Subcriticality Monitors for Accelerator-Driven Systems
MCNP-DSP Calculations of the 252Cf-Source-Driven Noise Analysis Measurements of Highly Enriched Uranium Metal Cylinders
Journal Article
·
Sat Dec 30 23:00:00 EST 1995
· Transactions of the American Nuclear Society
·
OSTI ID:186552
Coupling MCNP-DSP and LAHET Monte Carlo Codes for Designing Subcriticality Monitors for Accelerator-Driven Systems
Conference
·
Mon Oct 23 00:00:00 EDT 2000
·
OSTI ID:771590
MCNP-DSP Calculations of the 252Cf-Source-Driven Noise Analysis Measurements of Highly Enriched Uranium Metal Cylinders
Conference
·
Sun Sep 17 00:00:00 EDT 1995
·
OSTI ID:96845