Verification of a Three-Dimensional Nodal Transient Neutronics Routine for the TRAC-PF1/MOD3 Thermal-Hydraulic System Analysis Code-Reference-Cited by-同舟云学术

Verification of a Three-Dimensional Nodal Transient Neutronics Routine for the TRAC-PF1/MOD3 Thermal-Hydraulic System Analysis Code

Published:1998-07 Issue:1 Volume:123 Page:1-20
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Bandini Bernard R.¹,Ivanov Kostadin N.²,Baratta Anthony J.²,Steinke Robert G.³

Affiliation:

1. Bettis Atomic Power Laboratory P.O. Box 79, West Mifflin, Pennsylvania 15122

2. The Pennsylvania State University, Nuclear Engineering Department 231 Sackett Building, University Park, Pennsylvania 16802

3. Los Alamos National Laboratory P.O. Box 1663, Los Alamos, New Mexico 87545

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.13182/NT98-A2875

Reference11 articles.

1. N. M. SCHNURR et al. “TRAC-PF1/MOD2: Volume 1. Theory Manual,” LA-12031-M, Vol. I (NUREG/CR-5673), Los Alamos National Laboratory (1992).

2. B. R. BANDINI, “A Three Dimensional Transient Neutronics Routine for the TRAC-PF1 Reactor Thermal Hydraulic Computer Code,” PhD Thesis, The Pennsylvania State University, Department of Nuclear Engineering (1990).

3. P. E. ROHAN, S. G. WAGNER, and S. E. RITTERBUSCH, “HERMITE: A Multi-Dimensional Space-Time Kinetics Code for PWR Transients,” CENPD-188-A, Combustion Engineering, Inc. (1976).

4. L. D. EISENHART, “ARROTTA: Advanced Rapid Reactor Operational Transient Analysis Computer Code Documentation Package, Vol. 1: Theory and Numerical Analysis,” and “Vol. 2: User’s Manual,” Electric Power Research Institute (to be published).

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