Verification of a three-dimensional nodal transient neutronics routine for the TRAC-PF1/MOD3 thermal-hydraulic system analysis code

Nuclear Technology

Volumn 123, Issue 1, 1998, Pages 1-20

  Bandini, Bernard R ^a,b   Ivanov, Kostadin N ^b,d,e   Baratta, Anthony J ^b,f,g   Steinke, Robert G ^c,h  

^a BETTIS ATOMIC POWER LABORATORY   (United States)

^b PENNSYLVANIA STATE UNIVERSITY   (United States)

^c LOS ALAMOS NATIONAL LABORATORY   (United States)

^d MOSCOW POWER ENGINEERING INSTITUTE   (Russian Federation)

^e INSTITUTE FOR NUCLEAR RESEARCH AND NUCLEAR ENERGY   (Bulgaria)

^f Bulgarian Academy of Sciences ^*  (United States)

^g BROWN UNIVERSITY   (United States)

^h UNIVERSITY OF MICHIGAN   (United States)

Author keywords

Kinetics; Reactivity; Rod ejection

Indexed keywords

ACCIDENT PREVENTION; ALGORITHMS; COMPUTATIONAL METHODS; COMPUTER AIDED ANALYSIS; COMPUTER SOFTWARE SELECTION AND EVALUATION; CONTROL RODS; EIGENVALUES AND EIGENFUNCTIONS; HEAT CONDUCTION; REACTIVITY (NUCLEAR);

NEUTRONICS; NODAL EXPANSION METHOD; SOFTWARE PACKAGE ARROTTA; SOFTWARE PACKAGE HERMITE; SOFTWARE PACKAGE PF1/MOD3; THERMAL HYDRAULIC SYSTEMS;

PRESSURIZED WATER REACTORS;

EID: 0032121972     PISSN: 00295450     EISSN: None     Source Type: Journal    
DOI: 10.13182/NT98-A2875     Document Type: Article

References (13)

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