Abstract

Explosive research proves that there is a common cause for most explosions in nuclear reactor power plants during normal operations and accident conditions. The autoignition of flammable hydrogen is a common cause for nuclear power plant explosions, where complex corrosion processes, nuclear reactions, and thermal-fluid transients autoignite explosions. Research evaluated increasingly complicated accidents. First, piping explosions occurred at Hamaoka and Brunsbuttel. Fluid transients compressed oxygen and flammable hydrogen to heat these gases to autoignition, where resultant explosions shredded steel pipes. This identical mechanism was responsible for pipe and pump damages to U.S. reactor systems since the 1950s, where water hammer alone has been assumed to cause damages. Small explosions inside the piping actually cause damages during nuclear reactor startups and flow rate changes. Second, explosions are caused by thermal-fluid transients during nuclear reactor restarts, following accidental nuclear reactor meltdowns. Disastrous explosions destroyed nuclear reactor buildings (RBs) at Fukushima Daiichi. Previously considered to be a fire, a 319 kilogram hydrogen explosion occurred at Three Mile Island (TMI). The explosion cause following each of these loss-of-coolant accidents was identical, i.e., after meltdowns, pump operations heated gases, which in turn acted as the heat source to autoignite sequential hydrogen explosions in reactor systems to ignite RBs. Third, the Chernobyl explosion followed a reactor meltdown that was complicated by a high energy nuclear criticality. The hydrogen ignition and explosion causes are more complicated as well, where two sequential hydrogen explosions were ignited by high-temperature reactor fuel.

References

1.
Leishear
,
R.
,
2017
, “
Nuclear Power Plant Fires and Explosions—I, Plant Designs and Hydrogen Generation
,”
ASME Paper No. PVP2017-66285
.10.1115/PVP2017-66285
2.
Leishear
,
R.
,
2017
, “
Nuclear Power Plant Fires and Explosions, II, Hydrogen Ignition Overview,
ASME Paper No. PVP2017-66728
. 10.1115/PVP2017-66278
3.
Leishear
,
R.
,
2017
, “
Nuclear Power Plant Fires and Explosions, III, Hamaoka Piping Explosion,
ASME Paper No. PVP2017-66284
.10.1115/PVP2017-66284
4.
Leishear
,
R.
,
2017
, “
Nuclear Power Plant Fires and Explosions, IV, Water Hammer Ignition Mechanisms,
ASME Paper No. PVP2017-66279
.10.1115/PVP2017-66279
5.
Leishear
,
R.
,
2013
, “
From Water Hammer to Ignition, the Spark that Ignited Three Mile Island Burst From a Safety Valve
,”
ASME Mechanical Engineering Magazine
,
ASME Press
,
New York
, p.
4
.
6.
Leishear
,
R.
,
2017
,
Nuclear Power Plant Fires and Explosions, Accident Overviews
,
American Nuclear Society
,
LeGrange Park, IL
, p.
4
.
7.
Leishear
,
R.
,
2018
,
Pump Start-Ups Ignite Nuclear Power Plants: History, Law, and Risk
,
British Hydraulic Research Group
,
Cranfield, Bedfordshire, UK
, p.
16
.
8.
Leishear
,
R.
,
2011
, “
A Hydrogen Ignition Mechanism for Explosions in Nuclear Facility Pipe Systems
,”
ASME Paper No PVP2010-25261
.10.1115/PVP2010-25261
9.
Leishear
,
R.
,
2013
,
Fluid Mechanics, Water Hammer, Dynamic Stresses, and Piping Design
,
ASME Press
,
New York
.
10.
IAEA
, 2015, “
The Fukushima Daiichi Accident, Technical Volume 1, Description and Context of the Accident
,”
International Atomic Energy Agency
,
Vienna, Austria
.
11.
US
NRC
,
2018
, “
NuclearReactors,” U.S. Nuclear Regulatory Commission, Washington, DC, accessed Sept. 26, 2019
www.nrc.gov
12.
Draganac
,
I. G.
, and
Draganac
,
Z. D.
,
1971
,
The Radiation Chemistry of Water
,
Boris Kendric Institute of Nuclear Science
,
Vinca, Yugoslavia
, p.
242
.
13.
Hart
,
E. J.
,
Sauer
,
M. C.
,
Flynn
,
K. F.
, and
Gindler
,
J. E.
,
1976
, “
A Measurement of the Hydrogen Yield in the Radiolysis of Water by Dissolved Fission Products
,”
Argonne National Laboratory
,
Argonne, IL
, Report No. ANL-76-46.
14.
Naitoh
,
M.
,
Kasahara
,
F.
,
Mitsuhashi
,
T.
, and
Ohshima
,
I.
,
2003
, “
Analysis on Pipe Rupture of Steam Condensing Line at Hamaoka-1; Accumulation of Non-Condensable Gas in a Pipe, (I and II)
,”
J. Nucl. Sci. Technol.
,
40
(
12
), pp.
1032
1051
.10.3327/jnst.40.1032
15.
Lin
,
C. C.
,
1988
, “
The Radiolytic Gas Production Rate in Boiling Water Reactors
,”
Nucl. Sci. Eng. J.
,
99
(
4
), pp.
390
393
.10.13182/NSE88-A23567
16.
Baker
,
L.
, and
Just
,
C. J.
,
1962
, “
Studies of Metal-Water Reactions at High Temperatures III. Experimental and Theoretical Studies of the Zirconium-Water Reaction
,”
U.S. Nuclear Regulatory Commission
,
Washington, DC
, Report No. ML050550198.
17.
Ohta
,
T.
,
2009
, “
Energy Carriers and Conversion Systems With Emphasis on Hydrogen
,”
Encyclopedia of Life Support Systems
,
Yokohama National University
,
Kamakura, Japan
, pp.
131
146
.
18.
Turns
,
S.
,
2012
,
An Introduction to Combustion Concepts and Applications
,
McGraw-Hill
,
New York
.
19.
Glassman
,
I.
,
Yetter
,
R.
, and
Glumac
,
N.
,
2015
,
Combustion
,
Elsevier Press
,
Waltham, MA
, p.
758
.
20.
Schroeder
,
V.
, and
Holpettels
,
K.
,
2005
, “
Explosion Characteristics of Hydrogen-Air Mixtures at Elevated Pressures
,”
Bundesanstalt Fur Materialforschung Und-Pruefung
,
Berlin, Germany
.
21.
Lewis
,
B.
, and
von Elbe
,
G.
,
1987
,
Combustion, Flames, and Explosions of Gases
, 3rd ed.,
Academic Press
,
Orlando, FL
.
22.
Dryer
,
F. L.
,
Chaos
,
M.
,
Zhao
,
Z.
,
Stein
,
Jeffrey
,
J. N.
,
Alpert
,
Y.
, and,
Homer
,
C. J.
,
2007
, “
Spontaneous Ignition of Pressurized Releases of Hydrogen and Natural Gas Into Air
,”
Combust. Sci. and Technol.
,
179
(
4
), pp.
663
694
.10.1080/00102200600713583
23.
Krok
,
J.
,
1997
,
Jet Initiation of Deflagration and Detonation
,
California Institute of Technology
,
Pasadena, CA
.
24.
Yetter
,
R.
, and
Dryer
,
F.
,
1992
,
Major Research Topics in Combustion
,
M.
Hussaini
,
A.
Kumar
, and
R.
Voight
,
Springer-Verlag
,
New York
.
25.
Yamamoto
,
H.
,
2003
,
Revising Anomalous Explosion of Hydrogen and Oxygen Mixture From a Viewpoint of Cold Fusion
,
Japan CF Research Society
,
Morioka, Japan
.
26.
Papini
,
D.
,
Andreani
,
M.
,
Niceno
,
B.
, and
Prasser
,
H.
,
2015
,
Simulation of Hydrogen Distribution in the Containment During a Severe Accident With Fast Hydrogen-Steam Release
,
ASME
,
New York
.
27.
JAERI,
2001
,
The JAERI Group for Examination of the Ruptured Pipe at Hamaoka-1
,
Japan Atomic Energy Research Institute
,
Tokyo, Japan
.
28.
Nuclear and Industrial Safety Agency
,
2002
, “
Investigation Report on Pipe Rupture Incident at Hamaoka Nuclear Power Station Unit-1
,”
Ministry of Economy, Trade and Industry
,
Tokyo, Japan
.
29.
Leishear
,
R.
,
2013
, “
Explosions: A Fresh Look at Chernobyl, Three Mile Island, the Gulf Oil Spill, and Fukushima Daiichi
,”
Mensa World J.
, p.
1
.
30.
Schulz
,
H.
,
Voswinkel
,
A.
, and
Reck
,
H.
,
2001
, “
Insights and Lessons Learned From the Brunsbüttel Piping Failure Event
,”
Eurosafe
,
Cologne, Germany
.
31.
US NRC,
2008
,
Generic Letter 2008-01: Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems
,
U.S. Nuclear Regulatory Commission
,
Washington, DC
.
32.
US NRC
,
2015
, “
Control of Hydrogen During Normal Operations, PRE-GI-015 Enclosure, Response to R. Leishear
,”
U.S. Nuclear Regulatory Commission
,
Washington, DC
, Report No. ML16063A320.
33.
Henrie
,
J. O.
, and
Postma
,
A. K.
,
1982
,
Analysis of Three Mile Island Hydrogen Burn
,
U.S. Nuclear Regulatory Commission
,
Washington, DC
.
34.
NRC
,
1979
, “
Investigation Into the March, 28, 1979, Three Mile Accident by Office of Inspection and Enforcement
,”
NUREG
,
Washington, DC
, Report No. 50-320/79-10.
35.
NRC
,
2018
, “
Backgrounder of the Three Mile Island Accident
,”
U.S. Nuclear Regulatory Commission
,
Washington, DC
.
36.
Kemeny
,
J. G.
,
1979
, “
The Report of the President's Commission on the Accident at Three Mile Island
,”
The Presidents Commission on the Accident at Three Mile Island
,
Washington, DC
.
37.
Boucheron
,
E.
,
1991
, “
MELCOR Analysis of the TMI-2 Accident
,”
Sandia National Laboratories
,
Albuquerque, NM
.
38.
IAEA
,
2001
, “
Mitigation of Hydrogen Hazards in Severe Accidents in Nuclear Power Plants
,”
International Atomic Energy Agency
,
Vienna, Austria
, Report No. IAEA-TECDECDOC-1661.
39.
John
,
J. E. A.
,
1984
,
Gas Dynamics
,
Allyn and Bacon
,
Newton, MA
.
40.
Andrews
,
N.
, and
Gauntt
,
N.
, “
Insights Gained From Forensic Analysis With MELCOR of the Fukushima-Daiichi Accidents
,”
Sandia National Laboratory
,
Albuquerque, NM
.
41.
Fauske
,
H.
, and
Henry
,
R.
,
2017
,
Experimental Technical Bases for Evaluating Vapor/Steam Explosions in Nuclear Reactor Safety
,
American Nuclear Society
,
LeGrange Park, IL
.
42.
IAEA
,
1992
, “
INSAG-7, “The Chernobyl Accident: Updating of INSAG-1
,”
International Atomic Energy Agency
,
Vienna, Austria
.
43.
LANL
,
2000
, “
A Review of Criticality Accidents
,”
Los Alamos National Laboratory
,
Los Alamos, NM
.
44.
AEC
,
2011
, “
Additional Analysis of the SL-1 Excursion 2011-09-27 at the Wayback Machine. Final Report of Progress July Through October 1962, November 21, 1962
,”
U.S. Atomic Energy Commission, Division of Technical Information
,
Washington, DC
, Report No. IDO-19313.
45.
Knief
,
R. A.
,
2008
,
Nuclear Engineering, Theory and Technology of Commercial Nuclear Power
,
American Nuclear Society
,
LeGrange Park, IL
.
46.
U.S. Nuclear Regulatory Commission
,
1975
, “
WASH-1400, Reactor Safety Study (RSS)
,”
U.S. Nuclear Regulatory Commission
,
Washington, DC
.
47.
US NRC
, 2017, “
Regulatory Analysis Guidelines of the U.S. Nuclear Regulatory Commission
,”
U.S. Nuclear Regulatory Commission
,
Washington, DC
, Report No. NUREG/BR-0058.
48.
Modarres
,
M.
,
Kaminsky
,
M.
, and
Kristov
,
V.
,
2010
,
An Introduction to Reliability Engineering and Risk Analysis, A Practical Guide
,
CRC Press
,
New York
.
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