Production and Testing of the DNA Few-Group Coupled Neutron-Gamma Cross-Section Library

FIIDOS--A Computer Code for the Computation of Fallout Inhalation and Ingestion Dose to Organs Computer User's Guide (Revision 4)

“…As seen in Table 7, the first 15 gamma-ray spectrum energy groups from ORIGEN match the last 15 exposure factor energy groups from radiation transport cross section of DLC-31 (Bartine, 1977); however, the 16 th gamma-ray spectrum energy group (4.0 -6.0 MeV) encompasses both the 5 th th (5.0 -6.0 MeV) and the 6 (4.0 -5.0 MeV) exposure factor energy groups. To accommodate this mismatch, the 16 th gamma-ray spectrum energy group is subdivided into two groups with 55% of the gamma ray emission rate assigned to a 4.0 -5.0 MeV energy group and 45% of the emission rate assigned to a 5.0 -6.0 MeV energy group.…”

Cross Sections and Source Spectrum for Nagasaki Dose Reconstruction for Risk Estimation

“…Angular distributions are approximated using a P5 Legendre expansion. As in DLC-31 9 , the neutron groups are tailored to allow for the major peaks and valleys in the total neutron cross sections of nitrogen, oxygen, silicon, and iron. The photon groups are tailored to allow accurate calculation of pair production, annihilation photon transport, hydrogen capture, and backscatter photon transport.…”

A User's Manual for MASH V1.5 - A Monte Carlo Adjoint Shielding Code System

“…It should be noted that the interval next to the source interval will always exhibit greater than a factor of two difference in the fluence. A good rule of thumb for an air-over-ground calculation is to assume an initial [3][4][5][6][7] "source" interval size and apply a factor of 1.3 to that interval size to determine the interval boundaries. For example, assume the source is positioned at r-0.0 and the source interval is lO-cm wide.…”