Jan Blomstrand, Professor Emeritus
Chair of the Division of Nuclear Reactor
Engineering within the Department of
Energy Technology, Royal Institute of
Technology (KTH),
from
1994-09-01 until 2001-06-30.
LIST OF PUBLICATIONS
J. Blomstrand, L. Massimo, J. Schlösser
and E. Schröder, The
Dragon Core. Presented at the Thorium Fuel Cycle Symposium,
J. Blomstrand, J. Schlösser, H. Bruneder, U. Nyffenegger and G. Graziani, Uranium-235/Thorium Fuel Cycles in Graphite
Moderated Systems. Proceedings from the Conference “Fuel Cycles of High
Temperature Reactors”,
E. Schröder, J. H. Blomstrand and H.
Bruneder, Fuel Cycles for Power Reactors. Symposium
on High Temperature Reactors and the Dragon Project,
H. Paul and
J. H. Blomstrand, Determination of Fission Product
Activities in Graphite by Gamma Spectrometry. Journal of
Nuclear Energy, 1967, Vol. 21, pp. 183 – 191, Pergamon
Press.
J. H. Blomstrand, A Note on
Equilibrium Fuel Cycle Analysis. Journal of Nuclear
Energy, 1968, Vol. 22, pp. 687 – 697, Pergamon Press.
R. J. J. Stamm´ler, J. Blomstrand and Z.
J. Weiss, Equivalence Relations for Resonance Integral
Calculations. Journal of Nuclear Energy, 1973,
Vol. 27, pp. 885 – 888, Pergamon Press.
S-Å. Andersson and J.
H. Blomstrand, A
J. H. Blomstrand and S-Å. Andersson,
BWR Core Response to Fluctuations in Coolant Flow and Pressure, with
Implications on Noise Diagnosis and Stability Monitoring. Topical Meeting
on Advances in Reactor Physics and Core Thermal Hydraulics,
J. H. Blomstrand and S. A. Andersson, Recording,
Evaluation and Interpretation of Process Noise in ASEA-ATOM BWRs.
Fourth Specialist Meeting on Reactor Noise (SMORN IV), Dijon, France, 15 – 19
October, 1984. Progress in Nuclear Energy, 1985, Vol. 15, pp. 461 – 471. Pergamon Press.
J. Blomstrand, A. Ljungblad, J.
Johansson, B. Hedkrok, G. Wiksell,
S. Persson, S. Övrum and L.
Åberg, Cycle Extension in ASEA-ATOM BWRs. Nuclear Europe No. 3, March 1986, pp. 29 – 31.
O. Nylund and J. Blomstrand, Current
Experience and Development Aspects of SVEA BWR Fuel. International
Symposium on Improvements in Water Reactor Technology and Utilisation,
J. Blomstrand, A.
Spencer, J. Ganea, L. Ekstam, P. Reibe, K. Adielsson, F. Schwarts, Ch. Kvarnström
and L-E. Häll, Noise Analysis of Core Coolant
Channel Flow Signals, Recorded in Swedish and Finnish BWRs.
Fifth Specialist Meeting on Reactor Noise (SMORN V),
S. Andersson, J. Blomstrand and Ch. Jönsson, Experimental Investigations on BWR Core and
Coolant Channel Flow Stability. Presented at the
Stability Symposium/TRAC-BWR Workshop organised by EG&G,
J. Blomstrand, H. Broddfelt, L. Holm
and S. Haque, Stability Investigations on SVEA-64
BWR Fuel. Proceedings Fourth International Topical Meeting on Nuclear
Reactor Thermal-Hydraulics (NURETH-IV), Karlsruhe,
Germany, 10 – 13 October 1989; Vol. 1, pp. 521 – 527.
J. Blomstrand, Th. Lindqvist, J. Lorentzen, B-G. Bergdahl, R. Oguma, B. Andersson, P. Reibe and P. Lansåker, Stability
Investigations of Forsmark 1 BWR during Power
Ascension after the Annual Shutdown of 1987. International Workshop on
Boiling Water Reactor Stability,
J. Blomstrand, O. Nylund and R. Eklund, Flow Stability Investigations of SVEA BWR fuel.
International Workshop on Boiling Water Reactor Stability,
J. Blomstrand and H. Sonntag, Recent
Core Stability Trends Experienced in the KKB BWR. Proceedings Jahrestagung Kerntechnik 1992, 5 – 7
May, Karlsruhe, Germany, pp. 97 – 100.
J. Blomstrand, C. Rotander and S.
Lundberg, Core Stability Monitoring – On-line Performance Qualification of
COSMOS in KKL. Proceedings
Jahrestagung Kerntechnik 1993, 25 – 27 May, Cologne, Germany, pp. 361 – 364.
J. Blomstrand, C. Rotander, S. Lundberg and C-G. Wiktor, Operational Experience of Core
Stability in KKL, Gained from Tests conducted in 1990 and 1993. Proceedings Jahrestagung Kerntechnik 1994,
17 – 19 May, Stuttgart, Germany, pp. 73 – 76.
J. Blomstrand, B. Ludtke, R. Lundmark and H. Sonntag, Core
Stability Tracking of the KKB BWR in Recent Years. Nuclear Engineering and
Design 154 (1995), pp. 27 – 41.
H. Wennerström, W. Frid and J. Blomstrand, The Effect of Oxidation on the Minimum Film
Boiling Temperature on a Heated Vertical Surface. Presented
at the 34th European Two-Phase Flow Group Meeting,
T. Okkonen, H. Wennerström, S. Hedberg, J. Blomstrand, B. R. Sehgal and W.Frid, Film
Boiling on a Long Vertical Surface under High Heat Flux and Water Subcooling Conditions. Presented at the 31st National
Heat Transfer Conference,
F. D´Auria, W. Ambrosini, T. Anegawa, J. Blomstrand, J. In De Betou, S. Langenbuch, T. Lefvert and K. Valtonen, State
of the Art Report on Boiling Water Reactor Stability (SOAR on BWRs). NEA/CSNI/R(96)21,
OCDE/GD(97)13. January 1997.
H. Wennerström, W. Frid and J. Blomstrand, The Effect
of Surfactants on the Leidenfrost Temperature. Presented at the 35th European Two-Phase Flow Group
Meeting,
H. Wennerström, W. Frid and J. Blomstrand, The Effect of Oxidation on the Minimum Film
Boiling Temperature on a Heated Vertical Surface. Presented
at the 35th European Two-Phase Flow Group Meeting,
J. Blomstrand, R. Carlsson and M. Petersson, Studies of Thermal-Hydraulic Flow Stability
of two Designs Versions of the SVEA BWR Fuel Assembly, based on Signal
Recordings made in the Forsmark 2 Plant over the
years 1990 – 1995. Proceedings from the BNES TopFuel
´97 Conference, Manchester, UK, 9 – 11 June 1997, Vol. 2, pp. 5.67 – 5.77.
S. Erixon, S. Appelgren, S. Eriksson
and J. Blomstrand, The Impact on Safety of the
Integrity of Internal Parts in three Swedish Boiling Water Reactors of
Identical Design. Presented at the ENS TopSafe ´98
J. Blomstrand, R. Carlsson and M. Petersson, Studies of Channel Flow Stability in a
Boiling Water Reactor. Presented at the 2nd International
Symposium on Two-Phase Flow,
D. Behamin, P. Persson, S. Hedberg and J. Blomstrand, Loop
Studies Simulating – in Annular Geometry – the Influence of Spacers on Dryout in 8x8 BWR Assemblies. Presented
at the 37th European Two-Phase Flow Group Meeting,
J. Blomstrand, D. Behamin, P. Persson and S. Hedberg, Loop
Studies Simulating – in Annular Geometry – the Influence of the Axial Power
Distribution and the Number of Spacers on Dryout in
8x8 BWR Assemblies. Presented at the ENS TopFuel
2001 Conference,
H. Sadeghi, S. Hedberg, P. Fernando
and J. Blomstrand, Loop Studies of Void Contents
and Pressure Drop Characteristics of Air-Water Flows through two Transparent Mockups of BWR Core Coolant Channels, at Pressures slightly
above Atmospheric. Presented at the 40th
European Two-Phase Flow Group Meeting,
LIST OF PATENTS
7506606-8 Reactor
with a borated pool
81029525-8 BWR
core stability monitoring system
8204269-8 Fuel
assembly for a BWR
8504811-4 SVEA
Fuel assembly 5x5
8602515-2 Suppression
of noise interference