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Search indexed NASA NTRS and DOE OSTI research on propulsion, heat transfer, battery materials and energy systems. Follow report and document links to the original sources.

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At least 127 records · Page 7
All sourcesNASA NTRSDOE OSTI
DOE OSTI2016

A Complete Reporting of MCNP6 Validation Results for Electron Energy Deposition in Single-Layer Extended Media for Source Energies <= 1-MeV

In this paper, we expand on previous validation work by Dixon and Hughes. That is, we present a more complete suite of validation results with respect to to the well-known Lockwood energy deposition experiment. Lockwood et al. measured energy deposition in materials including beryllium, carbon, aluminum, iron, copper, molybdenum, tantalum, and uranium, for both single- and multi-layer 1-D geometries. Source configurations included mono-energetic, mono-directional electron beams with energies of 0.05-MeV, 0.1-MeV, 0.3- MeV, 0.5-MeV, and 1-MeV, in both normal and off-normal angles of incidence. These experiments are particularly valuable for validating electron transport codes, because they are closely represented by simulating pencil beams incident on 1-D semi-infinite slabs with and without material interfaces. Herein, we include total energy deposition and energy deposition profiles for the single-layer experiments reported by Lockwood et al. (a more complete multi-layer validation will follow in another report).

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗
DOE OSTI2017

MCNP6 simulated performance of Micro-Pocket Fission Detectors (MPFDs) in the Transient REActor Test (TREAT) Facility

Micro-Pocket Fission Detectors (MPFDs) are under development for in-core neutron flux measurements at the Transient REActor Test facility (TREAT) and in other experiments at Idaho National Laboratory (INL). The sensitivity of MPFDs to the energy dependent neutron flux at TREAT has been determined for 0.0300-μm thick active material coatings of 242 Pu, 232 Th, natural uranium, and 93% enriched 235 U. Self-shielding effects in the active material of the MPFD was also confirmed to be negligible. Lastly, fission fragment energy deposition was found to be in conformance with previously reported results.

36 MATERIALS SCIENCE↗
DOE OSTI2013

MCNP6 Dose Calculations for the Carousel in the LDRGIF

All calculated results are satisfactory. The 66% confidence intervals for all results are less than 5%. A comparison was made between a simple model and a detailed model. The simple model consists of the source, room walt the carousel AI disks, sample cans, and the samples. The detailed model includes the entire simple model along with the safe, and all of the details of the carousel. There was no difference between the two models for the dose absorbed by the samples. If these calculations are performed in the future, one should use the simple model. The simple model runs faster and the results are easier to understand. Dose rates to various polymers in the carousel assembly were calculated. The source of radiation is a 6.61 curie 137 Cs source. The experiments are planned for Bldg 6631. LK3626 absorbed the largest dose, 791000±554 rads/yr. The lowest absorbed dose is 696000±487 rads/yr. The lowest absorbed dose is for the gold disk #1 and TLDs 1a and 1b, Au disk 658000±3950 rads/yr and TLD 1a 481000±4450 rads/yr. The Au disk with the highest absorbed dose is #3 at 3640000±9460 rads/yr. The TLD with the highest absorbed dose is 6a at 1820000±106 rads/yr.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗
DOE OSTI2014

MCNP6 Class

This report provides a Monte Carlo method for simulating radiation transport and provides a common sense approach for MCNP.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗