Status report; Reactor shield codes for personal computers

Journal Article · Thu Jan 01 04:00:00 EST 1987 · Radiation Protection Management; (United States)

OSTI ID:5282998

Parsons, D K; Nigg, D W; Yoon, W Y ^[1]

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1. EG and G Idaho, Inc., Idaho Falls, ID (US)

This paper reports that as part of project to d develop a package of reactor physics codes for Personal Computers (PCs), the Idaho National Engineering Laboratory (INEL) is developing microcomputer versions of two reactor shielding codes that previously were available for mainframe computers only: QAD-CG and ANISN. QAD-CG is a point kernel code for gamma ray shielding calculations that is similar to MICROSHIELD. ANISN is a well known one-dimensional discrete ordinates transport theory code for reactor design, criticality, and shielding. Of the two, QAD-CG is most frequently used for gamma shielding calculations, while ANISN is better suited for calculations involving neutrons and/or gammas when scattering needs to be treated more accurately.

• OSTI ID: 5282998
• Journal Information: Radiation Protection Management; (United States), Journal Name: Radiation Protection Management; (United States) Vol. 4:1; ISSN 0740-0640; ISSN RPMAE
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
220900 -- Nuclear Reactor Technology-- Reactor Safety
A CODES
COMPUTER CALCULATIONS
COMPUTER CODES
COMPUTER-AIDED DESIGN
CRITICALITY
DESIGN
DISCRETE ORDINATE METHOD
ELECTROMAGNETIC RADIATION
GAMMA RADIATION
IDAHO NATIONAL ENGINEERING LABORATORY
IONIZING RADIATIONS
KERNELS
NATIONAL ORGANIZATIONS
ONE-DIMENSIONAL CALCULATIONS
PHYSICS
PLANNING
POINT KERNELS
Q CODES
RADIATION PROTECTION
RADIATIONS
REACTOR COMPONENTS
REACTOR PHYSICS
REACTOR SAFETY
SAFETY
SHIELDING
US DOE
US ERDA
US ORGANIZATIONS