vladimir artisyuk - esi.nus.edu.sg

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

1 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


(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


(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


(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


(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


(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

http://wwwndc.jaea.go.jp/

The First-in-the-World

Nuclear Reactor

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”

Reactor physics vs reactor

technology “Dеvil in the details”

2. Nuclear technology

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%


CANDU (Canada Deuterium Uranium)

Heavy water

water

Low neutron capture

(heavy water) Natural uranium:

U-235 – 0.7%


+

http://www.nucleartourist.com/

http://www.thestar.com/

CANDU (Canada Deuterium Uranium)


RMBK:

1-st generation of Russian NP

technology

+ Medium neutron capture

(graphite)

Slightly enriched uranium:

U-235 – 2%


!

NPP with RBMK

On the top of the

reactor


Light Water Reactors

High neutron capture

(waterН O) 2

Enriched uranium:

U-235 – 3-5% +

Glance at Pressurized Water and Boiling Water Reactors


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


http://ru.wikipedia.org/wiki/%D0%A4%D0%B0%D0%B9%D0%BB:Wwer-1000-scheme.png

Review of Nuclear Reactors

Find difference!


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.


Specific of Fuel Assemblies

PWR BWR

WWER


Specifics of Fuel Pellets

To reduce thermal stress

and pressure on the fuel

cladding


Fuel Burnup

%3235 U %5235 U

fuelt

dayGWtB


Modern Concepts of Light Water Reactors



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


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

!


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


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)


Glance at Fuel Cycle


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/


World Uranium Mining

! ! Rosatom


From ROSATOM Report

!

Rosatom !

World Uranium Enrichment


From ROSATOM Report

Uranium enrichment in Russia


! Rosatom !

World Fuel Fabrication 1/2


From ROSATOM Report

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


FLOATING NPP KLT-40 TYPE

48

Installed capacity 70/38 MWe

Thermal power 50/146,8 Gcalh


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

From “Nuclear news” - the ANS Journal

Spent Fuel Options


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

1 July 2010

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

Issue of non-proliferation 4

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

Protection of Fuel Cycle

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

http://upload.wikimedia.org/wikipedia/commons/8/8b/Implosion_Nuclear_weapon.png






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)

Nuclear power technology

has an intrinsic potential for

sustainable development

Спасибо

(Spasibo)

Thank You!

[email protected]

Prof. Vladimir Artisyuk

mailto:[email protected]










vladimir artisyuk - esi.nus.edu.sg

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