Reactor physics calculations in the Nordic countries

Proceedings of the 7th Nordic Reactor Physics Meeting

Randolph Höglund (Editor)

Research output: Book/ReportBook (editor)Scientificpeer-review

Abstract

The seventh biennial meeting on reactor physics calculations in the Nordic countries was arranged by VTT Energy in Otaniemi, Espoo on May 8 - 9, 1995. Recent development and verification of the program systems of ABB Atom, Risø, Scandpower, Studsvik and VTT Energy was of course the main topic of the meeting. Benchmarking of the two assembly codes CASMO-4 and HELIOS is proceeding. Cross section data calculated with CASMO-HEX have been validated for the Loviisa reactors. On core analysis, ABB Atom described its latest core simulator version POLCA7 with the calculation environment Core Master 2 and the BWR core supervision system Core Watch. Transient calculations with HEXTRAN, HEXTRAN-PLIM, TRAB, RAMONA, SIMULATE-3K and a code based on PRESTO II/ POLCA7 were presented. The importance of an efficient core monitoring system for detection of various anomalies, as excessive crud accumulation or assembly bowing, was demonstrated. It was furthermore shown that reactor physics methods can be successfully applied to other problems, as charged particle transport, that core stability can be considerably improved through careful fuel and core design as well as optimum use of control rods, that ordinary diffusion theory sometimes may be surprisingly accurate also in extreme conditions, but that on the other hand even sophisticated programs can have a hard time when confronted with the exotic geometries of a test reactor. The old four-factor-formula was revived in an attempt to obtain better agreement between measurements and an uncomplicated theory. Criticality safety studies performed at VTT Energy and ex-core neutron flux calculations at ABB Atom were reported. Finally, both the calculation and measurement of void fractions were discussed during the meeting.
Original languageEnglish
Place of PublicationEspoo
PublisherVTT Technical Research Centre of Finland
Number of pages355
ISBN (Print)951-38-4550-8
Publication statusPublished - 1995
MoE publication typeC2 Edited books
EventReactor physics calculations in the Nordic countries: 7th Nordic Reactor Physics Meeting - Espoo, Finland
Duration: 8 May 19959 May 1995

Publication series

NameVTT Symposium
PublisherVTT
No.159
ISSN (Print)0357-9387
ISSN (Electronic)1455-0873

Fingerprint

reactor physics
congressional reports
assembly
reactors
control rods
atoms
diffusion theory
flux (rate)
clocks
simulators
energy
voids
safety
charged particles
anomalies

Keywords

  • nuclear reactors
  • reactor dynamics
  • nuclear energy
  • radiation hazards
  • measurement
  • calculations
  • computer codes
  • monitors
  • safety
  • physics

Cite this

Höglund, R. (Ed.) (1995). Reactor physics calculations in the Nordic countries: Proceedings of the 7th Nordic Reactor Physics Meeting. Espoo: VTT Technical Research Centre of Finland. VTT Symposium, No. 159
Höglund, Randolph (Editor). / Reactor physics calculations in the Nordic countries : Proceedings of the 7th Nordic Reactor Physics Meeting. Espoo : VTT Technical Research Centre of Finland, 1995. 355 p. (VTT Symposium; No. 159).
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Höglund, R (ed.) 1995, Reactor physics calculations in the Nordic countries: Proceedings of the 7th Nordic Reactor Physics Meeting. VTT Symposium, no. 159, VTT Technical Research Centre of Finland, Espoo.

Reactor physics calculations in the Nordic countries : Proceedings of the 7th Nordic Reactor Physics Meeting. / Höglund, Randolph (Editor).

Espoo : VTT Technical Research Centre of Finland, 1995. 355 p. (VTT Symposium; No. 159).

Research output: Book/ReportBook (editor)Scientificpeer-review

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N2 - The seventh biennial meeting on reactor physics calculations in the Nordic countries was arranged by VTT Energy in Otaniemi, Espoo on May 8 - 9, 1995. Recent development and verification of the program systems of ABB Atom, Risø, Scandpower, Studsvik and VTT Energy was of course the main topic of the meeting. Benchmarking of the two assembly codes CASMO-4 and HELIOS is proceeding. Cross section data calculated with CASMO-HEX have been validated for the Loviisa reactors. On core analysis, ABB Atom described its latest core simulator version POLCA7 with the calculation environment Core Master 2 and the BWR core supervision system Core Watch. Transient calculations with HEXTRAN, HEXTRAN-PLIM, TRAB, RAMONA, SIMULATE-3K and a code based on PRESTO II/ POLCA7 were presented. The importance of an efficient core monitoring system for detection of various anomalies, as excessive crud accumulation or assembly bowing, was demonstrated. It was furthermore shown that reactor physics methods can be successfully applied to other problems, as charged particle transport, that core stability can be considerably improved through careful fuel and core design as well as optimum use of control rods, that ordinary diffusion theory sometimes may be surprisingly accurate also in extreme conditions, but that on the other hand even sophisticated programs can have a hard time when confronted with the exotic geometries of a test reactor. The old four-factor-formula was revived in an attempt to obtain better agreement between measurements and an uncomplicated theory. Criticality safety studies performed at VTT Energy and ex-core neutron flux calculations at ABB Atom were reported. Finally, both the calculation and measurement of void fractions were discussed during the meeting.

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KW - calculations

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KW - monitors

KW - safety

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SN - 951-38-4550-8

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ER -

Höglund R, (ed.). Reactor physics calculations in the Nordic countries: Proceedings of the 7th Nordic Reactor Physics Meeting. Espoo: VTT Technical Research Centre of Finland, 1995. 355 p. (VTT Symposium; No. 159).