Isotropic analogs for radiation levels across off-core midplane penetrations
Creators
Description
This paper develops the isotropic analogs of fast neutron flux (energy > 1 MeV) and gamma dose rate at the core mid-plane and at a typical off-core midplane penetration, e.g., a recirculation line penetration. The authors use the basic methodology of evaluating radiation levels outside primary shield wall penetrations using isotropic analogs previously developed. The method developed and illustrated in this paper consists of combining one-dimensional transport analysis, e.g., ANISND, with experimental studies of variations in fast neutron flux and gamma dose rate for BWRs and simple penetration formulas generally available in textbooks. The application of this approach to pressurized water reactors is straightforward. As the analysis for core midplane and recirculation line penetrations presented here illustrates, the results of simplified analyses become increasingly conservative as the offset of penetration axis from core midplane increases
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 62
- Journal Page Range
- p. 447-448.
- ISSN
- 0003-018X
- CODEN
- TANSAO
Conference
- Title
- American Nuclear Society (ANS) winter meeting.
- Dates
- 11-16 Nov 1990.
- Place
- Washington, DC (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24038785
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- A CODES; BWR TYPE REACTORS; D CODES; GAMMA RADIATION; ISOTROPY; NEUTRON FLUX; PRIMARY COOLANT CIRCUITS; RADIATION DOSES; REACTOR CORES; SHIELDING; TWO-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- COMPUTER CODES; COOLING SYSTEMS; ELECTROMAGNETIC RADIATION; ENRICHED URANIUM REACTORS; IONIZING RADIATIONS; POWER REACTORS; RADIATION FLUX; RADIATIONS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-901101--.