LW SMR technology development. Think different… Design, technology and innovations. Safety. (Second edition) ID - OR USA 2013.

LW SMR technology

development.

Think different…

Design, technology and innovations. Safety. (Second edition)

ID - ORUSA 2013

Pre-words and Abbr… :

SMR – Small Modular Reactor LOFA – Loss of Flow Accident

Rr(s) – (Nuclear) Reactor(s) LOCA – Loss of Coolant Accident

NPP – (Naval) Nuclear Propulsion Plant LOHS – Loss of Heat Sink

FNPP – Floating Nuclear Power Plant CHF – Critical Heat Flux (I or II)

PP – Power Plant FE – Fuel Element (or pin)

LW SMR – Light Water SMR FI – Flow instabilities

SCWR – Super-Critical Water Reactor GEN – Generation (for Rr(s))

LMR – Liquid Metal Reactor D/S – dimensions and sizes

HTGR – High-Temperature Gas cooled Rr PCS – Primary Circuit System

SG – Steam Generator SCS – Secondary Circuit System

ConOps – Conception of Operations h/e(s) – heat exchanger(s)

BNT – (design) based on Naval Technology SL – Safety Limits

Talking about LW SMR:

1. SMR Worldwide

2. SMR Historical aspect (SU-Ru only)

3. SMR Conception Y/N

4. SMR Different designs

5. Development reasons

6. SMR RV dimensions

7. SMR Safety analysis

8. SMR Road map?

And: Perspective for new step to G5?

1. SMR Worldwide:

Res.Rs

Power.Rs

Naval.Ru

Naval.US

Naval.etc

Place SMRs in the reactors World fleet:

• Experimental and Researches Rr(s) – 750

• Naval Rr(s) – (USSR - Russia 490, USA ~ 270, etc. ~ 30)

• Power Rr(s) – 440 (+140) in building, licensing, design or planning)

We can not ignore naval experience in design, development SMR…

2.1. History (SU-Ru only):

NPP Index: Development (lead) and operating time:

Civilian:

2WD New Generation     IV.2

FNPP M.Lomonosov     GEN-III.2

KLT-40 & 40M (2+1)   LWR GEN - III.1

OK-900* & 900A (1+6)   LWR GEN - II.2

BM-A (1) Lenin*   LWR GEN - I LWR GEN - II.1

Naval:

OK-550   LMR GEN - II

BM-1 LMR   LMR GEN - I

"Phenix" (?)     GEN - V  

TM-4 or KNT-6     LWR GEN - IV     LWR GEN - IV  

OK-650, OK-900 (SS)   LWR GEN - III

BM-5   LWR GEN - II.2     LWR GEN - II.3

OK-300, OK-350 (700)   LWR GEN - II.1   LWR GEN - II.1

BM-A   LWR GEN - I

1950 1955 1960 1965 1970 1975 1980 1985 1990 1995 2000 2005 2010 2015 2020

2.2. History (SU-Ru NIB only):

3. SMR conception Y/N?

SMR in the modern and right/correct understanding:

• Small – From 3 aspects of D/S: compact Rr design, PP constructional sizes, and site size (not including resources)

• Relatively Modular – From 2 aspects of modularity: in Rr and main components (Rr interns) design, and modularity mostly in PP

• Advanced design? (core - 40 y/old, SG, h/e(s), s-systems today)

• In-depth & advanced Rr passive safety for reactor and systems (?)

• Modern technology and advanced project process (soft, simulations scientific and training – Yes, and…)

… but, not only something else:

• New materials (core, SG, h/e(s)). We are in XXI century…

• Advanced Rr operating algorithms and developed ConOps

• Reliability and Economy. Parameters and PP SMR efficiency?

• Decommission process from first design steps…

4. Different designs concepts:

Ways for SMR development projects today:

• From Large Power Reactors (> USA)

• From Naval reactors and systems (> Russia)

• Independent projects based on own and exported new/advanced technology, and designs (Argentina, China, Korea, India, etc., all “sponge” -countries)

• LW SMR – next 40… 50 yrs

• SCWR – perspective 20… and up to…

• Etc.

• LMR – perspective for 20… and up to…

• HTGR – perspective for 20… and up to…

Type of SMR perspective for today and or tomorrow:

5. SMR development reasons:

SMR development reasons for today (?):

• Decentralized electrical-grids development as part of Energy National Security Policy (USA)

• North and Fare East territories development (Russia, Canada, USA-?). Example: 4 DCV via North-Iced Ocean in 2011, 46 in 2012, 372 in 2013 (at least 15 days shorter voyage)

• New technology and industry development (USA - ?, Argentina, China, Korea, India, and other developing countries). 08/12/2013 first Naval LW PWR in India and Argentinian project - critical aspect for development

6. SMR dimensions:

Reactors, SG and containments approximate D/S (w/out main and supporting systems):

• NuCore (BNT project + decommission cont.)*

• mPower (reactor only)

• NuScale

• Regular LWR:

7. LW SMR Safety analysis:

7.1. LW SMR SL problem statement:7.2. LW SMR SL classification diagram(s):7.3. Core/Fuel SL and new fuel options:7.4. H-T vs. T-H, flow regimes, FI and SL: 7.5. LW SMR NC and no interferences aspects:7.6. LW SMR operating & control aspects:7.7. LW SMR NC design specials:

7.1. LW SMR SL statement:

What happened after …?

This happened

because …

Core Safety aspects:

Rr. Safety aspects:

PCS Safety aspects:

SCS Safety aspects:

PP Sub-Sys safety:

P-loss:

RoPower & WR

Tau

T1C

P1CH1C

LOCA

M-flow LOFA

T2C P2C P FW

P4C

Com E-Powr

SeismicA-

Crash

Control Systems

:

Human factor:

Fair Etc.

External events:

DG E-Powr

BB E-Powr

LOHS-LOFA

Ops & controlDesign Plans?

Reactor C-Sys

Other C-sys

CHF I

7.2. LW SMR SL diagram:

7.3. Core/Fuel SL and new fuel:

7.4. H-T vs. T-H & flow regimes:

7.5. LW SMR NC and no:

7.6. LW SMR operating/control:

7.7. LW SMR NC design:

8. SMR development R-map:

Main problems and/or issues for inventors, designers, scientists:• Fuel composition – UO2 (new reactors with >35 y/old feel) substitution

to different matrix and type as alternative Si+C (?)

• Fuel cladding – Zr-cladding substitution to SS and alloys, or Si+C (?)

• Core configuration and design – “standard/well known” core is not acceptable for NC…

• SG design – d-Pressure through 1C and 2C and S-Sys always problems

• Rr(s) sizes and dimensions – +/-

• Reactor control and operating algorithms development and optimizations …

• ConOps (PP with SMR operating procedures) …

• Parameters 1C and 2C optimizations …

• Economical (efficiency) problems solutions …

• Licensing … (no good examples here)