Published May 20, 1985 | Version v1
Miscellaneous

ZZ AIRFEWG, Gamma, Neutron Transport Calculation in Air Using FEWG1 Cross-Section

Description

1 - Description of program or function: Format: ANISN; Number of groups: 37 neutron / 21 gamma-ray; Nuclides: air (79% N and 21% O); Origin: DLC-0031/FEWG1 cross sections (ENDF/B-IV). Weighting spectrum: 1/E. The AIRFEWG library has been generated by an ANISN multigroup calculation of gamma-ray, neutron, and secondary gamma-ray transport in infinite homogeneous air using DLC-0031/FEWG1 cross sections. 2 - Method of solution: The results were generated with a P3, ANISN run with a source in a single energy group. Thus, 58 such runs were required. For sources in the 37 neutron groups, both neutron and secondary gamma-ray fluence results were calculated. For gamma-ray sources only gamma-ray fluences were calculated

Availability note (English)

Available on-line: http://www.nea.fr/abs/html/dlc-0049.html

Additional details

Publishing Information

Imprint Pagination
[html]

INIS

Country of Publication
Nuclear Energy Agency of the OECD (NEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
40018249
Subject category
S99: GENERAL AND MISCELLANEOUS;
Resource subtype / Literary indicator
Computer Program Description, Non-conventional Literature
Descriptors DEI
AIR; COMPUTER PROGRAM DOCUMENTATION; CROSS SECTIONS; GAMMA RADIATION; GAMMA SOURCES; MULTIGROUP THEORY; NEUTRON TRANSPORT; NEUTRONS; NUCLEAR DATA COLLECTIONS; PHOTON TRANSPORT; RADIATION DOSES; SHIELDING; WEBSITES; Z CODES
Descriptors DEC
BARYONS; COMPUTER CODES; DOCUMENT TYPES; DOSES; ELECTROMAGNETIC RADIATION; ELEMENTARY PARTICLES; FERMIONS; FLUIDS; GASES; HADRONS; IONIZING RADIATIONS; NEUTRAL-PARTICLE TRANSPORT; NEUTRON TRANSPORT THEORY; NUCLEONS; RADIATION SOURCES; RADIATION TRANSPORT; RADIATIONS; TRANSPORT THEORY

Optional Information

Notes
1 ref.