Published August 1989 | Version v1
Report Metadata-only

Neutron streaming benchmark calculations

Creators

  • 1. Oak Ridge National Lab., TN (USA). Radiation Shielding Information Center
  • 2. Korea Advanced Energy Research Inst., Daeduk (Republic of Korea)

Description

Computational techniques used to analyze neutron streaming through cavities and ducts are described. The configurations are simplified geometries of streaming paths which can be found in nuclear fission and fusion reactors. The results obtained using available computational tools are compared to each other

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS, PC A06/MF A01 as DE89015664; OSTI; INIS; US Govt. Printing Office Dep.

Additional details

Publishing Information

Imprint Pagination
99 p.
Report number
ORNL/RSIC--52

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
21014092
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY; S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
BENCHMARKS; COMPUTER CALCULATIONS; CONCRETES; DOSE RATES; DUCTS; M CODES; MONTE CARLO METHOD; NEUTRON FLUX; NEUTRON SPECTRA; PWR TYPE REACTORS; R CODES; RADIATION STREAMING; REACTOR SAFETY; SHIELDING; STAINLESS STEELS
Descriptors DEC
ALLOYS; BUILDING MATERIALS; CARBON ADDITIONS; COMPUTER CODES; ENRICHED URANIUM REACTORS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; POWER REACTORS; RADIATION FLUX; REACTORS; SAFETY; SPECTRA; STEELS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Contract/Grant/Project number
Contract AC05-84OR21400