Canada’s HWR Technology - iaea.orgJBall).pdf2014 Nov 24-28, J. Ball Canada’s HWR Technology. ......

-1-UNRESTRICTED / ILLIMITÉ

Update/Proposed Activities

2014 Nov 24-28, J. Ball

Canada’s HWR Technology


UNRESTRICTED / ILLIMITÉ

National Status on HWR & Related

R&D

•HWR Plants in Canada

19 power reactor units operating

Bruce 1-8, Darlington 1-4, Pickering 1, 4-8, Point LePreau

•Refurbishment Activities:

Several planned refurbishments.

Bruce 3-4, Bruce 5-8, Darlington 1-4

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UNRESTRICTED / ILLIMITÉ

National Status on HWR & Related R&DOperating HWR Plants in Canada

0%

10%

20%

30%

40%

50%

60%

70%

80%

90%

100%

Pe

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nta

ge

Gro

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Ca

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cit

y F

ac

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From COG Database, 2012-03

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• Ontario Power Generation unveiled its new training facility for the refurbishment of the Darlington nuclear plant, the first of its kind in the world. The facility features a life-size model of a nuclear reactor face

• The first refurbishment project in the world to use a full-scale replica for training – with a mock-up of the reactor vault that is accurate to within 30 millimetres.

• refurbishment is expected to provide an additional 30 years of service for the nuclear station.

New Technology DevelopmentTraining Facility. Darlington Refurbishment


New Technology DevelopmentNuclear Refurbishment Schedule

Source: Ontario Long Term Energy Plan 2013


Future Role & Initiatives on HWRs

In 2013, the Government of Canada announced its intention to implement a Government-owned, Contractor-operated (GoCo) model for the management of AECL’s Nuclear Laboratories. The implementation of the GoCo model entails two steps.

• Creation of CNL as a subsidiary of AECL, to be operated with the governance, management systems and workforce in place under AECL.

• Transfer of ownership of to the new GoCo contractor (autumn of 2015). At that time, CNL will become a private-sector entity

AECL will oversee the performance of the contractual obligations of the contractor and retain ownership of the Nuclear Laboratories’ physical and intellectual property assets and its liabilities.

AECL Restructuring


Future Role & Initiatives on HWRs-

On November 3, AECL launched a wholly-owned subsidiary named Canadian Nuclear Laboratories (CNL). CNL will focus on three key mandates going forward:

• Managing Canada’s radioactive waste and decommissioning responsibilities accumulated during more than 60 years of nuclear research and development at the Chalk River and WhiteshellLaboratories.

• Ensuring that Canada's world-class nuclear science and technology capabilities and knowledge continue to support the federal government in its nuclear roles and responsibilities — from health protection and public safety to security and environmental protection.

• Providing access to industry, on a commercial basis, to address its need for in- depth nuclear science and technology expertise.

AECL Restructuring


New Technology Development

Post Fukushima, AECL mobilized an integrated project team (the Fukushima Response Project) to improve emergency response capability and implement a Severe Accident Management Program (SAMP) for the Chalk River site.Requirements and recommendations from reviews of the lessons learned from the Fukushima accident were addressed (e.g., Canadian Nuclear Safety Commission (CNSC) and World Association of Nuclear Operators (WANO))Differences between Nuclear Power Plants (NPPs) and NRU precluded the application of SAMP elements developed by the industry partners to NRU, much of the SAMP development work at AECL has been unique to NRU and the CRL site.

Responding to Future Significant Events, CRL Site Activities



Equipment and organizational changes needed to fully support the implementation of SAMP and to mitigate severe accidents in NRU have been identified and changes are being implementedTraining and developing the validation activities (e.g., tests, drills and exercises) are currently being completedA SAMP validation exercise currently planned for 2015A feature of many of these exercises is validation of AECL’sabilities to fulfill its roles defined in within the Federal Nuclear Emergency Plan

Responding to Future Significant Events, CRL Site Activities



An AECL-CNSC Nuclear Safety Technology seminar and information exchange takes place annually to exchange current R&D information between AECL (CNL) and CNSC and to identify priorities for the federal S&T program on Nuclear Safety Technology. The 2014 seminar (entitled PHWR Safety 2014) was extended to international participants operating Pressurized Heavy Water Reactor and was held in Ottawa, Canada, in partnership with CANDU Safety Association for Sustainability (CANSAS), IAEA, Canadian Nuclear Society, and Korean Nuclear SocietyIssues identified this year included PAR response to D2. An evaluation is currently being performed.

Responding to Future Significant Events – Federal S&T



CNL and CNSC are generating a web-based reference document on plant-specific severe accident analysis results and plant design information in a searchable electronic form called the Nuclear Power Plant Accident Handbook for the Emergency Operations Centre (EOC) at the CNSCCNL and CNSC have contracted the development of animation software, GRaphical Animation Package Extension (GRAPE), a user-friendly interactive interface to the Canadian Industry’s MAAP-CANDU severe accident code. The interface will allow assessment of the effect of implementing severe accident management measures in a nuclear power plant.

Responding to Future Significant Events – Federal S&T


New Technology DevelopmentTesting of PAR for Severe Accident Conditions – Industry S&T

CABS Rig Prepared for New and Lab-Degraded PAR Catalyst Testing


New Technology DevelopmentExperimental Studies to Support In-Vessel Retention – Industry S&T

CV Bottom CHF Apparatus CV with obstructionsEnd Shield CHF – Main Test

Immersion of the heater block in a transparent tank of waterSealing accomplished around periphery of block with gasketsUnheated extensions provided to direct 2-phase flow

Addition of a second heated

plate in place of an unheated

extension

Pressing a machined

obstruction against the boiling

surface using a fixed metal plate

Phase I – Direct HeatingPhase IIa – Thick Copper Plate with Cartridge HeatingGeneral progression from simple and easily achievable to more complex and representative of reactor geometry


New or Revised Proposals for Future IAEA

Activities

Objective: to provide a central database of numerical benchmarks of PHWR transients and best-estimate solutions. Specific milestones include:

• State-of-the-art report (SOAR) detailing current approaches in the area of 3-D

neutronics / thermalhydraulic coupled simulations in PHWR operating countries. The

SOAR will provide a list of PHWR transients which could be rendered as numerical

benchmarks within the database.

• Requirement for the database, including precision thresholds and convergence

criteria for the numerical benchmark sample solutions and external submissions.

• Benchmark specifications, and sample solutions, for two PHWR transients to be

included in the database.

• The publication of a summary of all participant-contributed solutions to the first two

benchmarks.

Database of numerical benchmarks of PHWR transients and best-

estimate solutions

Canada’s HWR Technology - iaea.orgJBall).pdf2014 Nov 24-28, J. Ball Canada’s HWR Technology. ......

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