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Title: NAUA-MOD5

Abstract

NAUA-MOD5 and NAUA-MOD5/M calculate the behaviour of a polydisperse aerosol system in a closed container. This container can be subdivided into a number of subcompartments geometrically separated but coupled by gas flows. For NAUA-MOD5/M an arbitrary configuration of subcompartments and flow patterns can be treated.

Authors:
Publication Date:
Research Org.:
OECD Nuclear Energy Agency
Sponsoring Org.:
USDOE
OSTI Identifier:
1279655
Report Number(s):
NAUA-MOD5; 002327MNFRM00
Resource Type:
Software
Software Revision:
00
Software Package Number:
002327
Software Package Contents:
Media Directory; Software Abstract; / 1 CD-ROM
Software CPU:
MNFRM
Source Code Available:
No
Country of Publication:
United States

Citation Formats

Sartori, Enrico. NAUA-MOD5. Computer software. Vers. 00. USDOE. 16 Apr. 2007. Web.
Sartori, Enrico. (2007, April 16). NAUA-MOD5 (Version 00) [Computer software].
Sartori, Enrico. NAUA-MOD5. Computer software. Version 00. April 16, 2007.
@misc{osti_1279655,
title = {NAUA-MOD5, Version 00},
author = {Sartori, Enrico},
abstractNote = {NAUA-MOD5 and NAUA-MOD5/M calculate the behaviour of a polydisperse aerosol system in a closed container. This container can be subdivided into a number of subcompartments geometrically separated but coupled by gas flows. For NAUA-MOD5/M an arbitrary configuration of subcompartments and flow patterns can be treated.},
doi = {},
year = {Mon Apr 16 00:00:00 EDT 2007},
month = {Mon Apr 16 00:00:00 EDT 2007},
note =
}

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  • RELAP4/MOD5, Update 1 was released to the Nuclear Regulatory Commission in January 1976. Six months of extensive use of Update 1 has led to the identification and correction of a number of errors in the code, as well as some logic changes, additional Evaluation Model (EM) checks, and one model revision. These changes have culminated in the release of an improved code identified as RELAP4/MOD5, Update 2. The RELAP4/MOD5 interim User's Manual (Interim Report SRD-113-76) reflected the Update 1 version of the code. The purpose of the supplement presented is to update the Interim User's Manual for use with RELAP4/MOD5,more » Update 2. Major differences between Updates 1 and 2 and the checkout of Update 2 are discussed. The final version of the User's Manual will be written in accordance with Update 2 and will be published as ANCR-NUREG 1335 during September 1976. Annotation of the existing three volumes of the User's Manual to cross-reference this Supplement is recommended.« less
  • A detailed description is presented of the RELAP4/MOD5 computer program. RELAP4 is written in FORTRAN IV for analysis of nuclear reactors and related systems. It is primarily applied in the study of system transient response to postulated perturbations such as coolant loop rupture, circulation pump failure, power excursions, etc. The program was written to be used for water cooled (PWR and BWR) reactors and can be used for scale models such as LOFT and SEMISCALE. Additional versatility extends its usefulness to related applications, such as ice condenser and containment subcompartment analysis. Specific options are available for reflood (FLOOD) analysis andmore » for the Evaluation Model.« less
  • RELAP4 is a computer program written in FORTRAN IV for the digital computer analysis of nuclear reactors and related systems. It is primarily applied in the study of system transient response to postulated perturbations such as coolant loop rupture, circulation pump failure, power excursions, etc. The program was written to be used for water-cooled (PWR and BWR) reactors and can be used for scale models such as LOFT and SEMISCALE. Additional versatility extends its usefulness to related applications, such as ice condenser and containment subcompartment analysis. Specific options are available for reflood (FLOOD) analysis and for the NRC Evaluation Model.
  • MOD5 calculates the time- and energy-dependent evolution of the neutron density in homogeneous media following initiation of a) a monoenergetic source distributed over a finite time interval, or b) a source of arbitrary spectrum with a delta-function distribution in time. Effectively the code produces Green's function solutions to the slowing-down equation in discrete numerical form. Leakage is treated in the diffusion approximation. The program a) calculates spectra and energy moments at selected times following the burst of source neutrons, b) evaluates the time-dependent neutron density and slowing-down density at selected energies and computes moments of these densities, c) calculates time-dependentmore » distributions of capture, leakage and first fission, and moments of these distributions, d) calculates steady-state central core neutron flux and leakage flux in detail and in group-averaged form, and e) calculates parameters such as keff.IBM360; FORTRAN IV; IBM360 CP-CMS; 175K bytes memory, normal input, output, program, and punch units, 6 cylinders of IBM2314 or equivalent direct-access storage.« less

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