메뉴 건너뛰기




Volumn 3, Issue , 2008, Pages 1789-1796

Coupled neutronics / thermal hydraulics calculations for high temperature reactors with the DALTON - THERMIX code system

Author keywords

[No Author keywords available]

Indexed keywords

CODES (SYMBOLS); HIGH TEMPERATURE REACTORS; HYDRAULICS;

EID: 70449640636     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper
Times cited : (13)

References (10)
  • 6
    • 33847242939 scopus 로고    scopus 로고
    • Summary of Comparison and Analysis of Results from Exercises 1 & 2 of the OECD PBMR Coupled Neutronics/Thermal Hydraulics Transient Benchmark
    • P. Mkhabela, e. a. (2006). Summary of Comparison and Analysis of Results from Exercises 1 & 2 of the OECD PBMR Coupled Neutronics/Thermal Hydraulics Transient Benchmark. In PHYSOR-2006, ANS Topical Meeting on Reactor Physics, Vancouver,BC,Canada.
    • (2006) PHYSOR-2006, ANS Topical Meeting on Reactor Physics, Vancouver, BC, Canada
    • Mkhabela, P.1
  • 7
    • 0242460568 scopus 로고    scopus 로고
    • DORT-TD: A Transient Neutron Transport Code with Fully Implicit Time Integration
    • Pautz, A. and Birkhofer, A. (2003). DORT-TD: A Transient Neutron Transport Code with Fully Implicit Time Integration. Nuclear Science and Engineering, 145:299-319.
    • (2003) Nuclear Science and Engineering , vol.145 , pp. 299-319
    • Pautz, A.1    Birkhofer, A.2


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.