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Experimental and analytical studies for the validation of HTR-VGD and primary cell passive decay heat removal. Supplement. Measurements. Final report; Experimentelle und analytische Arbeiten zur Absicherung von Druckbehaeltereinheit und Primaerzelle des HTR-Modul. Nebenband. Messtechnische Begleitung; Abschlussbericht

Abstract

The alternative concept for a modular HTR-reactor design by Siempelkamp, Krefeld, using a prestressed cast iron vessel (VGD) combined with a cast iron/concrete module for the primary cell with integrated passive decay heat removal system was fully qualified with respect to operational and accidental thermal loads. The main emphasis was to confirm and validate the passive decay heat removal capability. An experimental facility (INWA) was designed, instrumented and operated with an appropriate electrical heating system simulating steady-state operational and transient accidental thermal loads. The experiments were accompanied by extensive computations concerning the combination of conductive, radiative and convective energy transport mechanisms in the different components of the VGD/primary cell structures, as well as elastic-plastic stress analyses of the VGD. In addition, a spectrum of potential alternatives for passive energy removed options have been parametrically examined. The experimental data clearly demonstrate that the proposed Siempelkamp-design is able to passively and safely remove the decay heat for operational and accidental conditions without invalidating technological important thermal limits. This also holds in case of failures of both the natural convection system and ultimate heat sink by outside concrete water film cooling. (orig./HP) [Deutsch] Das von der Firma Siempelkamp, Krefeld, vorgeschlagene HTR-Modul Konzept mit  More>>
Publication Date:
Apr 01, 1993
Product Type:
Technical Report
Report Number:
BF-R-40056-02
Reference Number:
SCA: 220900; 210300; PA: DEN-94:0F2405; EDB-94:044717; ERA-19:012256; NTS-94:019334; SN: 94001162722
Resource Relation:
Other Information: PBD: Apr 1993
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; PEBBLE BED REACTORS; AFTER-HEAT REMOVAL; HTGR TYPE REACTORS; MODULAR STRUCTURES; REACTOR SAFETY; REACTOR ACCIDENTS; HEAT SINKS; NATURAL CONVECTION; REACTOR SAFETY EXPERIMENTS; COMPUTER CALCULATIONS; CAST IRON; PRESSURE VESSELS; PRESTRESSED CONCRETE; PRIMARY COOLANT CIRCUITS; VERIFICATION; 220900; 210300; POWER REACTORS, NONBREEDING, GRAPHITE MODERATED
Sponsoring Organizations:
Bundesministerium fuer Forschung und Technologie, Bonn (Germany)
OSTI ID:
10131480
Research Organizations:
Battelle-Institut e.V., Frankfurt am Main (Germany). Geschaeftsbereich Energie- und Verfahrenstechnik
Country of Origin:
Germany
Language:
German
Other Identifying Numbers:
Other: ON: DE94747574; CNN: Foerderkennzeichen BMFT 03BTI2035; TRN: DE94F2405
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
DEN
Size:
370 p.
Announcement Date:
Jul 04, 2005

Citation Formats

Haefner, W, Kneer, A, and Schulz, R. Experimental and analytical studies for the validation of HTR-VGD and primary cell passive decay heat removal. Supplement. Measurements. Final report; Experimentelle und analytische Arbeiten zur Absicherung von Druckbehaeltereinheit und Primaerzelle des HTR-Modul. Nebenband. Messtechnische Begleitung; Abschlussbericht. Germany: N. p., 1993. Web.
Haefner, W, Kneer, A, & Schulz, R. Experimental and analytical studies for the validation of HTR-VGD and primary cell passive decay heat removal. Supplement. Measurements. Final report; Experimentelle und analytische Arbeiten zur Absicherung von Druckbehaeltereinheit und Primaerzelle des HTR-Modul. Nebenband. Messtechnische Begleitung; Abschlussbericht. Germany.
Haefner, W, Kneer, A, and Schulz, R. 1993. "Experimental and analytical studies for the validation of HTR-VGD and primary cell passive decay heat removal. Supplement. Measurements. Final report; Experimentelle und analytische Arbeiten zur Absicherung von Druckbehaeltereinheit und Primaerzelle des HTR-Modul. Nebenband. Messtechnische Begleitung; Abschlussbericht." Germany.
@misc{etde_10131480,
title = {Experimental and analytical studies for the validation of HTR-VGD and primary cell passive decay heat removal. Supplement. Measurements. Final report; Experimentelle und analytische Arbeiten zur Absicherung von Druckbehaeltereinheit und Primaerzelle des HTR-Modul. Nebenband. Messtechnische Begleitung; Abschlussbericht}
author = {Haefner, W, Kneer, A, and Schulz, R}
abstractNote = {The alternative concept for a modular HTR-reactor design by Siempelkamp, Krefeld, using a prestressed cast iron vessel (VGD) combined with a cast iron/concrete module for the primary cell with integrated passive decay heat removal system was fully qualified with respect to operational and accidental thermal loads. The main emphasis was to confirm and validate the passive decay heat removal capability. An experimental facility (INWA) was designed, instrumented and operated with an appropriate electrical heating system simulating steady-state operational and transient accidental thermal loads. The experiments were accompanied by extensive computations concerning the combination of conductive, radiative and convective energy transport mechanisms in the different components of the VGD/primary cell structures, as well as elastic-plastic stress analyses of the VGD. In addition, a spectrum of potential alternatives for passive energy removed options have been parametrically examined. The experimental data clearly demonstrate that the proposed Siempelkamp-design is able to passively and safely remove the decay heat for operational and accidental conditions without invalidating technological important thermal limits. This also holds in case of failures of both the natural convection system and ultimate heat sink by outside concrete water film cooling. (orig./HP) [Deutsch] Das von der Firma Siempelkamp, Krefeld, vorgeschlagene HTR-Modul Konzept mit einem vorgespannten Gussdruckbehaelter und einem in die Primaerzelle integriertem passiven Nachwaermeabfuhrsystem wurde sicherheitstechnisch qualifiziert mit Schwerpunkt auf einem experimentellen Funktionsnachweis fuer das passiv wirkende Nachwaermeabfuhrsystem. Es wurde ein Versuchsstand konzipiert und aufgebaut und die Energiefreisetzung aus dem Reaktorkern ueber eine Heizeinrichtung simuliert. Das experimentelle Untersuchungsprogramm (INWA) wurde durch umfangreiche Berechnungen abgesichert. Diese Analysen umfassten die Simulation von Waermetransportvorgaengen, Spannungsanalysen des VGD, Uebertragung und Anwendung der Berechnungen auf Realanlagen, sowie Berechnungen von Konvektionsmechanismen. Ergebnis: Das vorgestellte Reaktorkonzept unter den spezifizierten Betriebs- und Stoefallbedingungen sicher zu betreiben und die Nachwaerme ist vollstaendig ueber ein passives System abfuehrbar, ohne dass Temperaturgrenzwerte ueberschritten werden. (orig./HP)}
place = {Germany}
year = {1993}
month = {Apr}
}