vladimir artisyuk - esi.nus.edu.sg
TRANSCRIPT
Vladimir ARTISYUK
Russian Nuclear Education & Training:
Experience to Share with Potential Recipients of
Russian Nuclear Power Technology
and the Issue of Non-proliferation
National University of Singapore
8 March 2011
Challenge of nuclear education&training
1
2 Russian nuclear power technology (brief history
and specifics)
Contents
Issue of non-proliferation
3
4
Reactor physics in a nut-shell
Basics of reactor physics 1/6
(chain reaction)
Neutron of the
1-st generation
Neutron leakage
Parasitic neutron capture
Neutrons of the
2-nd generation
n3CsRbnU 1
0
143
55
90
37
236
92
1
0
235
92 U PuNpU 239
93
239
93
239
92
1
0
238
92 nU
Fission
1. Reactor physics
Basics of reactor physics 2/6
(cross-sections) U235
Fission reaction is
dominating for
any neutron
energy
U238
is fissioned only
by “fast”
neutrons
U
U
235
238
1000f
1f
1. Reactor physics
Basics of reactor physics 4/6
(neutron multiplication factor)
Number of neutrons in N-th generation
k= Number of neutrons in( N-1)-th generation
Number of
neutrons
(Fission
rate)
k >1 Sub-critical reactor Critical reactor
Time
Supercritical reactor
k <1 k =1
N(o)
0
U
Pa
Th
Np
230 231 232 233 234 235 236 237 238
Inf
Inf
Inf
78
14
2.35 d
1.31 d 27 d
7 d
22.3 m 24 d 1 d
Inf
13 68.9 yr
740 W/kg
48
Inf
xxx
Decay Heat
-decay
-decay
Critical mass, kg
T1/2
102
1.6+5 yr
2.5+5 yr
7.0 +8 yr
Basics of reactor physics 3/6
(critical mass)
Critical mass- is
minimum mass that
could sustain chain
reaction.
Optimum
configuration (to
avoid neutron
leakage) - sphere.
U-238 provides an
isotopic barrier
against proliferation
of nuclear materials
Natural isotopic
composition:
U-238 - 99.3 %
U-235 - 0.07 %
!
1. Reactor physics
Basics of reactor physics 5/6
(fission neutron spectrum)
Probability for fission neutron to
escape with particular energy
1 MeV
1 MeV
Maximum of
fission
cross-section
1. Reactor physics
Maximum fission
cross-section
U-235 natural isotopic
fraction 0.7%
U-238 natural isotopic
fraction99.3%
Average
energy of
fission
neutrons
Principle : to slow down neutrons (moderation) to minimum energy (thermal
energy- maximum fission cross-section) and avoid resonance parasitic
capture in U-238.
1. Reactor physics
Basics of reactor physics 5/6
(neutron moderation)
Difficult to
avoid resonance capture
Reactor with natural
uranium fuel
works!
k >1 k <1
moderator
fuel
Fuel arrangement
Heterogeneous Homogeneius
Reactor with natural
uranium fuel
Possible to
avoid resonance capture
1. Reactor physics
Principles of neutron moderation
Before interaction : After interaction :
Elastic scattering
Heavy nuclei:
Neutron energy loss is small
Light nuclei:
Energy loss is large
Neutron moderator- chemical elements with small atomic number and
small neutron capture cross-sections
!
1. Reactor physics
http://wwwndc.jaea.go.jp.
10-3
10-2
100
Neutron moderators
(comparison of parasitic capture
cross-section)
%99.99:1H
%01.0:2 DH
Natural isotopic
composition of
hydrogen isotopes
1. Reactor physics
To comrade Stalin I.V.
With this we report that
on 25, December 1946 in the Laboratory of Prof. Kurchatov the
research uranium-graphite pile was successfully put into
operation. Within the first days of its operation (25-26-27,
December) we succeeded to achieve a controlled chain
reaction. Uranium graphite pile contains 34800 kg of pure metal
uranium, 12900 kg of pure uranium oxide and 420000 kg of
high purity graphite. With the help of this uranium graphite pile
we could solve the problems of nuclear energy utilization.
28 December 1946
L. Beriya, I.Kurchatov, B.Vannikov, M. Pervukhin
The First Soviet reactor (report )
I.Kurchatov,
1. Reactor physics
The First Russian Reactor:
currently – museum at the
Kurchatov Institute,
Moscow
The-First-in-the-World
Nuclear Power Plant:
currently – museum at the
Institute for Nuclear Power
Engineering,
Obninsk
(100 km to Moscow)
Initial Steps of Russian Nuclear
Power Technology
1946
1954
1. Reactor physics
2 Russian nuclear power technology (brief history
and specifics)
Reactor physics & reactor technology
Basic commercial reactors
Fuel cycle
Brief on the State Atomic Energy Corporation
“ROSATOM”
Heterogeneous
reactor
Reactor concepts
Quality of
moderator
Quality of
fuel
Low neutron capture
(heavy water)
(D O) 2
Natural uranium:
U-235 – 0.7%
Medium neutron capture
(graphite)
Slightly enriched uranium:
U-235 – 2%
High neutron capture
(waterН O) 2
Enriched uranium:
U-235 – 3-5%
2. Nuclear technology
CANDU (Canada Deuterium Uranium)
Heavy water
water
Low neutron capture
(heavy water) Natural uranium:
U-235 – 0.7%
2. Nuclear technology
+
http://www.nucleartourist.com/
http://www.thestar.com/
CANDU (Canada Deuterium Uranium)
2. Nuclear technology
RMBK:
1-st generation of Russian NP
technology
+ Medium neutron capture
(graphite)
Slightly enriched uranium:
U-235 – 2%
2. Nuclear technology
!
Light Water Reactors
High neutron capture
(waterН O) 2
Enriched uranium:
U-235 – 3-5% +
Glance at Pressurized Water and Boiling Water Reactors
2. Nuclear technology
PWR
BWR
Russia : totally 69 WWER reactors
Leningrad-2 AES-2006 AES-2006 Novovoronezh-2
AES-92
2 units
First unit
NPP Kudankulam AES-91
2 units
VVER-1000
Tianwan,China
Great series
21 units
Small series
5 units
VVER-1000
Zaporizhzhia-1
VVER-1000
NVAES-5 Generation II
19 units
Generation I
16 units
VVER-440
Loviisa, Finland
VVER-440
NVAES-3
VVER-365
VVER-210
VVER-70
Reinsberg, East Germany
Presentation of Kurchatov Institute
I.Kurchatov A.Alexandrov
NPP with WWER
On the top of the
reactor
2. Nuclear technology
Specific of Cladding
long time experience with Zr 1% Nb alloy
F.Onimus et al. “Plastic deformation of irradiated Zirconium
alloys: TEM Investigations and Micro-Mechanical Modelling”,
J. of ASTN International, Vol.2, 2005
Extensive tests and over 20 years experience proved safe operation of cladding made of 1%Nb zirconium alloy E110 at temperature below 350 ºC. That value has been detected the lowest temperature for structural changes in material. Below 350 ºC there is no evidence of plastic deformation or any other mechanical phenomena. To improve plastic deformation resistance the E365 alloy (1% Nb, 1.5% Sn, 0.5%Fe) was introduced in 2000. Test results demonstrate that Zr1%Nb alloy in VVERs is more resistant to oxidation than Zircaloy (ZrSn alloy) in PWR.
2. Nuclear technology
Specifics of Fuel Pellets
To reduce thermal stress
and pressure on the fuel
cladding
2. Nuclear technology
2. Nuclear technology
APR-1400
Korea
WWER
Specifics of Design
(vertical vs horizontal steam
generator)
V.A. Mokhov
OKB «Gidropress»
WWER: Response to the current
challenges Development of advanced designs of generation 3+
AES 2006 – The main trends of
improvement are:
extension of the main equipment service life;
decrease in the metal consumption;
decrease in the RP dimensions (aimed at containment size decrease);
optimal use of the redundancy, independence and diversity principles in design of safety systems.
informatization of life cycle, introducing of datacentering technologies, 3D designing
2. Nuclear technology
I. Ivkov
JSC SPAEP
AES-2006
Main features of design • Maximum use of well proven
technical solutions and equipment • Double containment • Four trains of active safety systems
(4x100%; 4x50%) • Special engineering measures for
BDBA management (core catcher, H2 PARs, PHRS) based mainly on passive principles)
• Introduction of passive BDBA • Optimized schematic approach • Borated water storage tanks (pit-
tanks) placed inside containment • Enhanced autonomy of the plant
from outer power sources • Water cooled generators • Adjustable and repairable inner
containment tensioner system
!
2. Nuclear technology
Control of Severe Accidents
Technological scheme of corium
localization
Assembling of corium localization equipment
at Tianwan NPP
The equipment for localization of corium (ELC) has been developed to
ensure a safety control even in case of severe accidents of low probability
with core melting. First in the world this equipment has been installed at
NPPs: Tianwan NPP in China and Kudankulam NPP in India which is being
constructed.
Presentation of Kurchatov Inst., Egypt, Cairo, June 2010
Fuel Assembly Evolution Evolution is based on maximum unification and succession in
respect to the manufactured FAs and proven engineering solutions
S.A. Kushmanov
OKB«Gidropress» 2. Nuclear technology
AES 2010 Goals
Key values of performance characteristics
V.A. Sidorenko
NRC KI
• Availability factor is 93% or more
• Overall efficiency is 37.4% • Power plant internal
consumption is 6.4% of installed power
• Double containment is designed to sustain more than 20 ton airplane crash (up to 400)
• In site area (including circulating water system) is 300 m2/MW
• Architectural volume of two units NPP is 500 m3/MW or less
• The time span from a first concrete batch to reactor start-up is 45 months or less
2. Nuclear technology
Trends of reactor scrams from critical state
at Russian NPPs and worldwide (WANO
method)
1,80
1,1
0,4 0,4 0,4 0,4
0,3
0,5
0,2
0,5 0,46
0,370,38
0,20
0,390,29 0,32
0,39
1,7
1,4
1,1
1,0
1,1
0,9
0,7 0,7
0,6
0,9
0,7 0,7
0,6 0,6
0,51 0,60,49
0,45
0
1
2
1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009
Scra
ms p
er
7000 h
un
it o
pera
tio
n
Russian NPPs (Concern Rosenergoatom's data)
NPPs worldwide (WANO data)
2. Nuclear technology
ROSATOM provides implementation of the
policy of Russian Federation in the field of
nuclear energy:
• Sustainability of of nuclear power industry
•Sustainability of nuclear weapon industry
•Sustainability of nuclear and radiation
safety
Three Pillars of ROSATOM
http://www.rosatom.ru/wps/wcm/connect/rosatom/rosatomsite/aboutcorporation/
2. Nuclear technology
Research,
--------------
Transport
and
industrial
reactors
VVER-1000
Russia - 10
Ukraine - 12
Bulgaria- 2
China- 2
India - 2
Czechia - 2
Iran- 1
VVER-440 Russia- 6
Ukraine- 2
Armenia - 1
Finland - 2
Slovakia- 6
Czechia- 4
Hungary - 4
RBMK
Russia – 11
Fast
breeders Russia - 1
Fuel supplier for 76 power reactors out of 438 ones operated in the World
(17% of the World nuclear fuel market)
FAs for
AREVA NP
Germany,
the
Netherlands
Switzerland
Sweden
9 Units
World Fuel Fabrication 2/2
2. Nuclear technology Presentation of TVEL., Hanoi, Sept. 2010
Белоярская
Балаковская
Курская
Калининская
Кольская
Ленинградская
Смоленская
Билибинская
Волгодонская
Нововоронежская
Nuclear Power in Russia
10 NPP (32 units) = 24242 MW (el)
16% of electricity production.
2. Nuclear technology Presentation of ROSATOM., Hanoi, Sept. 2010
2006 2007 2008 2009 2010 2011 2012 2013 2014 2015 2016 2017 2018 2019 2020
Ka
lin
in 4
V
oro
nezh
2-1
Rosto
v 2
-Vo
ron
ezh
2-2
Ro
sto
v 3
Ro
sto
v 4
Len
ing
rad
2-1
Len
ing
rad
2-2
Le
nin
gra
d
2-3
Be
loya
rsk
4
Len
ing
rad
2-4
Niz
heg
oro
d 3
NEW BUILD: СURRENT STATUS
•Central NPP
•Nizhny NPP
•Seversk NPP
•South Urals NPP
•Tver NPP
Total of 10 units
Balt
ic 1
Balt
ic 2
ROSTOV 2
2009 – first criticality
2010 – connected to grid,
gradual increase of power
Sites explored, licenses for construction
obtained.
Actual timing and sequences of further works
would depend on economic recovery in the
country
2. Nuclear technology Presentation of ROSATOM., Hanoi, Sept. 2010
FLOATING NPP KLT-40 TYPE
48
Installed capacity 70/38 MWe
Thermal power 50/146,8 Gcalh
2. Nuclear technology Presentation of ROSATOM., Hanoi, Sept. 2010
NPP with WWER Type
Reactors
SLOVAKIA
NPP “Bohunice” 4 VVER-440 NPP “Mokhovce” 2 VVER-440
GERMANY
NPP “Nord” 4 VVER-440 NPP “Rheinsberg” 1 VVER-70
CZECH REP.
NPP “Dukovany” 4 VVER-440 NPP “Temelin” 2 VVER-1000
FINLAND
NPP “Loviisa” 2 VVER-440
CONSTRUCTED:
TOTAL – 66
outside Russia – 48
in operation – 52
under
CONSTRUCTION:
TOTAL – 12
outside Russia – 5
CHINA
NPP “Tianwan” 2 VVER-1000 Framework Agreement on the construction of the next 2 VVER-1000
UKRAINE
NPP “Zaporozhskaya” 6 VVER-1000 NPP «Rovenskaya» 2 VVER-1000 2 VVER-440 NPP “Khmelnitskaya” 2 VVER-1000 NPP “Youzhno-Ukrainskaya” 3 VVER-1000
ARMENIA
NPP “Мetsamor” 2 VVER-440
HUNGARY
NPP “Paks” 4 VVER-440
IRAN
NPP “Bushehr” 1 VVER-1000 under comissioning
INDIA
NPP “Kudankulam” 2 VVER-1000 under construction
NPP “Belene” 2 VVER-1000 under construction
BULGARIA
NPP“Кozloduy” 4 VVER-440 2 VVER-1000
2. Nuclear technology Presentation of ASE., Egypt, Cairo, June 2010
Relation of construction cost -
localization
High localization can significantly reduce the capital
cost of the project
Rela
tive
co
st
Localization level, %
Bu
lga
ria
Ind
ia
Ch
ina
Presentation of ASE , Hanoi, Sept. 2010
Challenge of nuclear education&training 3
Global challenge of nuclear education
Education vs training
Demands from new-comers
Russia: Status and experience to share with potential
recipients
• aging of nuclear personnel
• increasing demands in nuclear specialists in both developing countries
(expanding nuclear power) and developed countries (closing fuel cycles)
• lack of experts in developing countries
• unattractiveness of technical sciences
(in developed countries )- «hard sciences»- are really hard!
•specifics of nuclear power technology “globalness” and long consequences
Global Challenge of
Nuclear Education
3. Nuclear E&T
Investments vs Results*:
* Sekazi K. Mtingwa (Masachusets Institute of Technology) U.S. Workforce and Educational Facilities’
Readiness to Meet the Future Challenges of Nuclear Energy Proceedings of Global 2009,Paris, France,
September 6-11, 2009
Response in the USA
Number of Nuclear Chemistry PhD
1963-2003
3. Nuclear E&T
Conclusions:
The “bottle neck” is lack of professors
(not students!)
To become professor requires about 12-15 yrs!
«Bottle neck» of nuclear education
(conclusions of the IAEA)
3. Nuclear E&T
EU Council conclusions on the « need for skills in the nuclear field » (5 December 2008)
THE COUNCIL
…..
IS OF THE VIEW THAT it is essential to maintain in the European Union
a high level of training in the nuclear field.
….
from Van Goethem Post-FISA 2009 Workshop,25June 2009, Prague
Reaction in European Union
3. Nuclear E&T
ENEN-III Project as a reaction of European Union
from Christian Schönfelder Post-FISA 2009 Workshop,25June 2009, Prague
> ENEN III as part of FP7:
Euratom Fission Training Schemes (EFTS) in all areas of Nuclear
Fission and Radiation Protection
> Aim is to design, develop and implement training on
basic nuclear topics for non-nuclear engineers
design respectively construction challenges for generation III NPPs
design challenges for generation IV reactors
> Targeted at professionals working in nuclear organizations or their
contractors and subcontractors
> Ultimate goal: to establish a common certificate
(European Training Passport for continuous professional
development),
> thereby ensuring free mobility of the workforce within the EU
> Project duration 3 years, started in May 2009
3. Nuclear E&T
Challenge of nuclear E&T
The urgent need to modify nuclear education in
the universities
The urgent need to meet the increasing demands
in NPP staff for emerging nuclear power
programmes in developing countries
3. Nuclear E&T
Introductory Statement to Board of Governors
by IAEA Director General Yukiya Amano
1 March 2010 Vienna, Austria
We have already re-focussed our activities to help meet the needs of
newcomers to nuclear power. I firmly believe that access to nuclear
power should not be limited to developed countries. It should also be
available to interested developing countries to help them lift their
people out of poverty. Naturally, it is the sovereign right of every
Member State to decide whether or not to introduce nuclear power.
The Agency will provide as much assistance as possible to countries
which take this option. My goal is that Member States embarking on
the path towards introducing nuclear power should start to see
tangible progress in the years to come as a result of the Agency´s
efforts.
http://www.iaea.org/newscenter/statem
ents/2010/amsp2010n001.html
3. Nuclear E&T
Infrastructure development.
Recent international forums
February, 2010 April, 2010 February, 2011
3. Nuclear E&T
Expectation from the side of recipeints Technical Meeting
Topical Issues on Infrastructure Development:
Managing the Development of National Infrastructure for Nuclear Power
Vienna 9-12 February 2010-02-09
3. Nuclear E&T
63
The-First-in-the-World Nuclear Power Plant
27 June, 1954
2009- branch of Natioanal Research Nuclear University
MEPhI
1985- Obninsk Institute for Nuclear Power Engineering
1953- branch of Moscow Engineering&Physics Institute
(Ministry of Education&Science)
Central Institute
for Continuing Education&Training
1967
(SAEC “ROSATOM”)
Obninsk- cradle of the NPP
development
3. Nuclear E&T
Structure of E&T in Russia
Ministry of Education SC “ROSATOM”
Education Training
Dip
lEn
gin
eer
Dip
l Sp
ecia
list
Bach
elo
r
Maste
r
Aspirantura
(Dr course)
UNVERSITIES
On
the J
ob
Tra
inin
g
Qu
alific
atio
n
Up
gra
de
Bu
ildin
gn
ew
co
mp
ete
nces
Training
Centers on Site Institutes for
E&T
3. Nuclear E&T
Consortium of Nuclear Universities in
Russia
MEPhI
Tomsk National Politechnic University (TPU)
Moscow PowerUniversity (MEI)
Ivanovo Power University
Bauman Technical University-Moscow
Ural Sate Technical University
Totally 26 education establishments covering all the areas relevant to
NP development (from civil engineering to reactor core physics) ! 3. Nuclear E&T
Prior to 1992- “Soviet System of Education”
1992 Introduction of multi-level education in Russia
Diploma of
Specialist
/engineer
5-5.5 yrs 3 yrs
Regular course aspirantura
aspirantura
3 yrs
Bachelor
Degree Master
Degree
4 yrs 2
yrs
2003 Russia joined the Bologna Process
Degree of
Candidate in Science
Degree of
Candidate in Science
1999 Bologna Process started in Europe
Reform of Education
3. Nuclear E&T
Field of specialization
(title of the speciality - career training trajectoiry)
Nuclear Power Plants and Facilities
Course duration: 4 years Qualification upon graduation : Bachelor’s degree
Course duration: 2 years
Qualification upon graduation : Master’s degree
!
The specific of Russia is that, compared to western education
system, there is a university speciality “nuclear power plant and
installations” (Dipl of Eng) especially focusing the staffing of
Nuclear Power Plants.
Nuclear Power Plants and Facilities
3. Nuclear E&T
Contribution of Russian Universities
to NPP Personnel Training
Ivanovo Power University
Saratov Technical University
Obninsk branch of National
Research Nuclear University MEPhI
Tomsk Polytechnic University
Kursk Technical University
!
3. Nuclear E&T
Total– 258
4033
39 40 39
10
10
12 74
8
4
47
1
0
10
20
30
40
50
60
70
2006 2007 2008 2009 2010
Others
Nuclear Industry
NPPs
Job Placements for graduates of NPP Equipment
and Operation Department (2006 – 2010)
Obninsk branch of National
Research Nuclear University MEPhI !
3. Nuclear E&T
Nuclear education for foreign students-
investment in the future
27 October 2010
Obninsk, Russia Vietnamese New Year – 3 February 2011
3. Nuclear E&T
134
707
869
952
143
917
146
683
155 26200
Number of trained specialists 1972 - 2008
Experience of training foreign specialists
Russia and CIS
countries
Bulgaria
E-Germany
CZ
India
China
Iran Finland
Cuba
Hungary
3. Nuclear E&T Presentation of ROSENERGOATOM., Hanoi, Sept. 2010
adjustment
Design of
on-site training
center
Construction of on-site-training center
Completing the
development of E&T
programmes
Reactor
startup
License for NPP
construction
Start 1 yr 2 yr 3 yr 4 yr 5 yr
Completing
Preparation for
adjustment and
start up
Start of Full
Scale Simulator
License for NPP
operation Task order for
Full Scale
Simulator
Start for
construction of Full
Scale Simulator
General Traiing
(Russian
language)
Theoretical
courses
Practical
experience
On-job-training
(NPP)
Certification
Training of NPP Personnel (including on-the-job-training in the reference Russian NPP)
Educational program corresponds to the licensed requalification
program (equivalent to higher technical university education) > 100 hr
3. Nuclear E&T Presentation of ROSENERGOATOM., Hanoi, Sept. 2010
Training Experience for foreign NPP Personnel
Bushehr NPP (Iran),
Tianwan NPP (China),
Kudankulam NPP (India)
1999 - 2005
Totally – 900 pecialists
3. Nuclear E&T
Human Resource Development Technical Meeting
Topical Issues on Infrastructure Development:
Managing the Development of National Infrastructure for Nuclear Power
Vienna 9-12 February 2010-02-09
3. Nuclear E&T
Russian organizations
involved in training course
development
Dpt of Human Resource
ROSENERGOATOM
GIDRO
PRESS
RIAR
NPP
training
center AEP
IBRAE
MSZ
Sub-
contructors
CICET
branch
International
Training Center
Methodolog
y Center
NPP
CICET
NUCLEAR ENERGY COMPLEX
State Corporation “Rosatom”
Development of course materials
based on SAT approach
Development of
training courses
Development of
the on-the-job
training
programmes
ISTC
RMTC
3. Nuclear E&T
Schedule for staying in Russia (Obninsk), inc. Technical
Tour to Balakovo NPP
*AH– Academic Hour (45 min.) Totally 100 AH
23
Nove
mber
24
November
25
November
26
November
27
Novemb
er
28
Nove
mber
29
November
30
November
01
December
02
December
03
December
04
December
05 06 07 08 09 10 11 12
Dece
mber December
Arr
iva
l
Training
10 AH*
Training
10 AH
Training
10 AH
Training
10 AH
Holid
ay
Training
10 AH
Training
10 AH
Training
10 AH
Training
10 AH
Training
10 AH
Training
10 AH
Technical Tour to
Balakovo NPP
(by train) Dep
art
ure
3. Nuclear E&T
Awarding the Certificates to
the specialists from Nuclear Power Plant
Authority- Egypt
Courses:
bid invitation
Site selection&specification
(27 August 2010)
Courses:
Fuel design
Physical protection&security
(10 December 2010)
Totally 42 trainees! 3. Nuclear E&T
Course development
2010
•Bid invitation
•Site selection&specification
•Characteristics&design of nuclear fuel
•Security & physical protection of NPP
2011-
•NPP construction Project Management
•Emergency Preparedness and Safety Assurance During
Transportation of Radioactive materials
•Reactor island: physics& equipment for engineers
•Turbine Island: thermohydraulics&equipments for enginers
•Waste management
Each course Totally 100 AH + facility visit
3. Nuclear E&T
Conclusions:
E&T package to new-comer countries
Short term courses (1-3 weeks) English
for managers and specialists (infrastructure)
Training of NPP staff (2-3 yrs) English/Russian
for national specialists with Eng. Ms. degrees
University education (6 yrs) Russian
(Eng Dipl. “Nuclear power plant and facilities”)
3. Nuclear E&T
Experimental crticial assemblies*
Godiva (U-235) Np -237
From End of an Era for the Los Alamos Critical Experiments
Facility:History of critical assemblies and experiments (1946–
2004)David Loaiza
PWR
1 GWel
U
FP
235 3.3%
238
U
Pu
MA
235 0.8%
238
Fresh fuel
27,271 kg
246 kg
25.32 kg
951 kg
33
GWd/thm
Fission products
Minor Actinides
Plutonium
Uranium
Nuclear Fuel Composition
Fuel cycle protection: view point of fuel cycle analyst Advanced Concept of Fuel Cycle
Power
Fresh Fuel Current
LWR
FP MA,U,Pu
Fuel Storage
Fuel Fabrication
Reprocessing Disposal
U,Pu
Fuel Storage
MA,U,Pu
Advanced
reactor
Power
To drastically reduce attractiveness of nuclear materials for weapon
manufacturing
Terminology
IAEA
Proliferation Resistance
Fundamentals
for Future Nuclear
Energy Systems
Department of safeguards,
International Technical
Meeting,
Como, Italy, October 2002.
Proliferation resistance is that characteristic
of a nuclear energy system that impedes the
diversion or undeclared production of nuclear
material or misuse of technology by States in
order to acquire nuclear weapons or other
nuclear explosive devices.
Intrinsic proliferation resistance features
are those features that result from technical
design of nuclear energy systems including
those that facilitate the implementation of
extrinsic measures.
Extrinsic proliferation resistance measures
are those measures that result from States’
decisions and undertakings related to nuclear
energy systems.
IAEA
Proliferation Resistance
Fundamentals
for Future Nuclear
Energy Systems
Department of safeguards,
International Technical
Meeting,
Como, Italy, October 2002.
“Examples of [intrinsic proliferation
resistance] features might be
Uranium enrichment plants that
cannot be used to produce high
enriched uranium (i.e.uranium
enriched to greater than 20% in the
isotope 235U)”
Progress in Nuclear Energy, 1982,
Volume 10, pp. 161-220
Denaturing Fissile Materials
A.DeVolpi
“A 20% 235U weapon is
considered by weapons
experts to be “impractical”
because of its large, bulky
mass”
Sources Currently Used for Assessment of
Proliferation Resistant Properties for Uranium
Sources Currently Used for Assessment of
Proliferation Resistant Properties for Minor Actinides
L.Koch, et al, Nuclear Material Safeguards for P&T
European Commission – Joint Research Center
Institute for Transuranium Elements
Np – “has to be considered as weapon utilizable”
TRPU – “fortunately the transplutonium nuclides have
high spontaneous fission rate which requires…a
sophisticated implosion technique to avoid a preignition”
244Cm – “can be ruled out as weapon utilizable material
because of the high spontaneous fission”
Am – “in the expected isotopic mixtures would require a
highly sophisticated design to turn it into explosive
device. Nevertheless, one should not underestimate the
danger of nuclear explosions even with “fizzy yields”.
Sources Currently Used for Assessment
of Proliferation Resistant Properties for Plutonium
IAEAInformation Circular
(Unofficial electronic edition)
INFCIRC/153 (Corrected)
June 1972 GENERAL Distr.
Original: ENGLISH
The Structure and Content of Agreements Between the
Agency and States Required in Connection with the Treaty on
the Non-Proliferation of Nuclear Weapons
PART II
EXEMPTIONS FROM SAFEGUARDS
The Agreement should provide that the Agency shall, at the request of the State,
exempt nuclear material from safeguards, as follows:
• Special fissionable material, when it is used in gram quantities or less as a
sensing component in instruments;
• nuclear material, when it is used in non-nuclear activities in accordance with
paragraph 13 above, if such nuclear material is recoverable;
• Plutonium with an isotopic concentration of plutonium-238 exceeding 80%.
IAEA
238U 80% 235U 20%
FP 238Pu 239Pu 240Pu 241Pu 242Pu FP
238Pu Fissile
Pu
Protection of Nuclear Materials from Use in Weapon Manufacturing
•Safeguard
•Isotopic Dilution
•Radiation Protection
•Isotopic Radiation
Protection
Opinion on 80% 238Pu
"A STRATEGIC FRAMEWORK FOR PROLIFERATION RESISTANCE:
A SYSTEMATIC APPROACH
FOR THE IDENTIFICATION AND EVALUATION OF TECHNOLOGY OPPORTUNITIES TO
ENHANCE
THE PROLIFERATION RESISTANCE OF CIVILIAN NUCLEAR ENERGY SYSTEMS"
James A. Hassberger, Tom Isaacs, Robert N. Schock
Lawrence Livermore National Laboratory.
Livermore, USA
“Although…238Pu is capable of
sustaining a fast critical mass,
the International Atomic
Agency (IAEA) considers
plutonium containing more
than 80% 238Pu not weapons
usable because of its high
heat generation”
Mass
(kg)
Decay Heat
(W/kg)
Neutrons From Spontaneous Fissions
(n/g/s)
MCNP calculation
(JENDL 3.2)
Physical characteristics of isotopic barrier
essential for Protected Plutonium Production
Physical Characteristics of Heavy Metals
U
Pa
Th
Np
230 231 232 233 234 235 236 237 238
Inf
Inf
Inf
78
14
2.35 d
1.31 d 27 d
7 d
22.3 m 24 d 1 d
Inf
13 68.9 yr
740 W/kg
48
Inf
xxx
Decay Heat
-decay
-decay
Critical mass, kg
T1/2
102
1.6+5 yr
2.5+5 yr
7.0 +8 yr
Physical Characteristics of Heavy Metals
Am
Pu
Np
Cm
237 238 239 240 242 243 244 245
78
5 h
2.1 d
8.2 87 yr
570 W/kg
2
10 34 12 70 14.4yr
242m
13
141 yr
241
311 75
2800 W/kg
30 13 18.4 yr
xxx
Decay heat Neutrons of
Spontaneous
Fission (n/g.s)
(1.2) (150)
(0.07)
(1.0E+7)
(2.E-2) (910) (1700)
(2.6e+3)
Beta-decay
alpha-deacy
10
(0.05)
Significant Quantity “the approximate quantity of nuclear material in respect of which
…the possibility of making nuclear explosive device can not be excluded”.
(IAEA)
Mass Categorization
Bare Critical Mass (Nuclear Physics Properties)
Significant Quantity (Trends)
235U
233U
Pu
25
8
8
1
1
3
Proposed by Natural
Resources Defense
Council (1995)
Traditional
IAEA (1950s)
exception of that containing 238Pu more than 80%
Significant
Quantity (Trends for Plutonium)
8 1
Proposed by Natural
Resources Defense
Council (1995)
Traditional
IAEA (1950s)
Proposed by
Pellaud B. (2002)
exception of that containing 238Pu more than 80%
16
8 240Pu: < 17%
240Pu: < 30%
Category Content of 240Pu
(%)
SQ (kg)
High-grade <17 8
Low-grade 17-30 16
Depleted-
grade
>30 -
B.PELLAUD, Proliferation Aspects of Plutonium Recycling,
J.Nucl.Mat.Management, XXXI, No.1 (2002) 30
Plutonium Categorization
(stress on 240Pu)
Radionuclides Accumulated in PWR
(3 years of cooling after discharge)
PWR
1 GWel
U
FP
235 3.3%
238
U
Pu
MA
235 0.8%
238
Fresh fuel
27,271 kg 246 kg
25.32 kg
951 kg
33
GWd/thm
239
240
241
242 238
Np-237
Cm-245
0.09% 56.93%
Am-243
13.56%
1.46%
54.73%
26.22%
11.51%
6.08%
Am-241
26.26%
Am-242m
0.07%
Cm-243
0.03%
Cm-244
3.02%
Kessler G.(2004), Plutonium
Denaturing by 238Pu, COE-INES
Topical Forum on Protected Plutonium
Utilization for Peace and Sustainable
Prosperity, 1-3 March, Tokyo Institute
of Technology
Kessler G.(2006), Analysis for a Future
Proliferation Resistant Fuel Cycle,
Kernbrennstoffkreislauf, Heft-5-Mai
238Pu content 12%
238Pu content 6-8%
Plutonium Denaturation
(stress on decay heat of 238Pu to deteriorate
properties of chemical explosives)
Спасибо
(Spasibo)
Thank You!
Prof. Vladimir Artisyuk