Isoshld: A Computer Code for General Purpose Isotope Shielding Analysis

Abstract

a r e p e r f o r m e d by p o i n t k e r n e l i n t e g r a t i o n ; f o r most geometr i e s by S i m p s o n ' s r u l e n u m e r i c a l i n t e g r a t i o n . S o u r c e s t r e n g t h i n u n i f o r m o r e x p o n e n t i a l d i s t r i b u t i o n (where a p p l i c a b l e ) may b e c a l c u l a t e d by t h e l i n k e d f i s s i o n p r o d u c t i n v e n t o r y c o d e R I B D o r by o t h e r o p t i o n s a s d e s i r e d . B u i l d u p f a c t o r s a r e c a l c u l a t e d b y t h e code b a s e d on t h e number o f mean f r e e p a t h s o f m a t e r i a l b e t w e e n t h e s o u r c e and d e t e c t o r p o i n t s , t h e e f f e ct i v e a t o m i c number o f a p a r t i c u l a r s h i e l d r e g i o n ( t h e l a s t u n l e s s o t h e r w i s e c h o s e n ) , And t h e p o i n t i s o t r o p i c

Radiation dose calculation in the human body for building materials and soil exposure pathways

“…EXTDF calculates the external dose-rate factors for submersion in an infinite Cloud of radioactive materials, immersion in contaminated water, and direct exposure to plane or slab sources of contamination. The EXTDF code is a modification and enhancement of the well-known shielding code ISOSHLD (Engel et al, 1966). INTDF estimates the dose equivalents in a number of target organs from the activity in a given source organ based on ICRP 30 (1 982) models and biokinetic values for radionuclide residency and transport in the body.…”

Hanford Site National Environmental Policy Act (NEPA) characterization. Revision 7

“…A limited biotic transport capability is included that can simulate the results of BIOPORT/MAXI (McKenzie et al 1985). GENII contains a modified version of the shielding code ISOSHLD (Engle et al 1966; Simmons et al 1967) that creates f$ctors relating sources with various geometries to dose rates. An essentially unchanged version of DI"Y ) has been added for predicting doses from waste management operations to the public during periods as long as 10,OOO years.…”

Models Selected for Calculation of Doses, Health Effects and Economic Costs Due to Accidental Radionuclide Releases From Nuclear Power Plants

“…Data in the file are derived from that used by the code ISOSHLD (Engle et al 1966). Gamma energies and probabilities per disintegration are stored by the five energy groups.…”

“…The attenuation factor as a function of distance, shielding and photon energy is calculated (Engle et al 1966, Jaeger 1968 The thicknesses tj are distance by…”

“…2 are dependent on the energy of the photons and also on the effective atomic number of the scattering medium. Engle et al (1966) have discussed treatment of buildup for multi-region shields. The approach they used, which is probably sufficient for the current application, was to consider all the mean free paths in material between the source and detector, using only the buildup coefficients of the last shield region.…”