Practical Elimination

The term “practical elimination” appeared for the first time in 1993 in the definition of the general safety objectives for the future pressurised water reactors.

The most recent international texts, particularly those issued by WENRA and the IAEA, state that “practical elimination” should be applied to core melt situations likely to lead to early or large releases.

Paragraph 2.13(4) of SSR-2/1 (Rev. 1) states:

“The safety objective in the case of a severe accident is that only protective actions that are limited in terms of lengths of time and areas of application would be necessary and that off-site contamination would be avoided or minimized. Event sequences that would lead to an early radioactive release or a large radioactive release are required to be ‘practically eliminated.”

An early radioactive release in this context is a radioactive release for which off-site protective actions would be necessary but would be unlikely to be fully effective in due time. A ‘large radioactive release’ is a radioactive release for which off-site protective actions that are limited in terms of lengths of time and areas of application would be insufficient for the protection of people and of the environment.

So situations likely to lead to large releases, because of the simultaneous or successive loss of integrity of all the containment barriers or because of the bypass of these barriers (containment bypass situations):

  • either lead to define provisions allowing to significantly limit their consequences
  • or shall be “practically eliminated”

The event sequences for which specific demonstration of their ‘practical elimination’ is required should be classified as follows:

  • Events that could lead to prompt reactor core damage and consequent early containment failure, such as:
    • Failure of a large pressure-retaining component in the reactor coolant system;
    • Uncontrolled reactivity accidents or rapid reactivity insertion accidents, in particular those caused by rapid injection of insufficiently borated water in the reactor core
  • Severe accident sequences that could lead to early containment failure, such as:
    • High-pressure core melt accidents that could lead to direct containment heating
    • Large in-vessel and ex-vessel steam explosions
    • Explosion of combustible gases, including hydrogen and carbon monoxide.
  • Severe accident sequences that could lead to late containment failure:
    • Basemat penetration or containment bypass during molten core-concrete interaction (MCCI)
    • Long term loss of containment heat removal
    • Explosion of combustible gases, including hydrogen and carbon monoxide
  • Severe accidents with containment bypass, such as core melt accidents with containment bypass via the steam generators or the loops connected to the RCS.
  • Significant fuel degradation in a storage fuel pool and uncontrolled releases.

Practical elimination” of such accident situations can be demonstrated by deterministic and/or probabilistic considerations, taking into account the uncertainties due to the limited knowledge of some physical phenomena. This demonstration can be based on various aspects such as:

  • Physical impossibility. For example, a reactor with negative αT is inherently stable to changes in its temperature and thermal power. This significantly limits consequences of reactivity initiated ccidents.
  • Extremely unlikely conditions.

For some external hazards it may not be not practical or even possible to demonstrate that the occurrence of a hazard of such severity that could cause extensive plant damage leading to a large or early radioactive release, and therefore needing to be practically eliminated, is below a threshold of frequency such as 10-6/year.

Plant States

nuclear power plant states - accident conditions

Nuclear and Reactor Physics:
  1. J. R. Lamarsh, Introduction to Nuclear Reactor Theory, 2nd ed., Addison-Wesley, Reading, MA (1983).
  2. J. R. Lamarsh, A. J. Baratta, Introduction to Nuclear Engineering, 3d ed., Prentice-Hall, 2001, ISBN: 0-201-82498-1.
  3. W. M. Stacey, Nuclear Reactor Physics, John Wiley & Sons, 2001, ISBN: 0- 471-39127-1.
  4. Glasstone, Sesonske. Nuclear Reactor Engineering: Reactor Systems Engineering, Springer; 4th edition, 1994, ISBN: 978-0412985317
  5. W.S.C. Williams. Nuclear and Particle Physics. Clarendon Press; 1 edition, 1991, ISBN: 978-0198520467
  6. G.R.Keepin. Physics of Nuclear Kinetics. Addison-Wesley Pub. Co; 1st edition, 1965
  7. Robert Reed Burn, Introduction to Nuclear Reactor Operation, 1988.
  8. U.S. Department of Energy, Nuclear Physics and Reactor Theory. DOE Fundamentals Handbook, Volume 1 and 2. January 1993.

Nuclear Safety:

  1. IAEA Safety Standards, Safety of Nuclear Power Plants: Design, SSR-2/1 (Rev. 1). VIENNA, 2016.
  2. IAEA Safety Standards, Safety of Nuclear Power Plants: Commissioning and Operation, SSR-2/2 (Rev. 1). VIENNA, 2016.
  3. IAEA Safety Standards, Deterministic Safety Analysis for Nuclear Power Plants, SSG-2 (Rev. 1). VIENNA, 2019.
  4. IAEA TECDOC SERIES, Considerations on the Application of the IAEA Safety Requirements for the Design of Nuclear Power Plants, IAEA-TECDOC-1791. VIENNA, 2016.
  5. Safety Reports Series, Accident Analysis for Nuclear Power Plants with Pressurized Water Reactors. ISBN 92–0–110603–3. VIENNA, 2003.
  6. Appendix A to 10 CFR Part 50, “General Design Criteria for Nuclear Plants.”
  7. NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition.
  8. Nuclear Power Reactor Core Melt Accidents, Science and Technology Series. IRSN – Institute for Radiological Protection and Nuclear Safety. ISBN: 978-2-7598-1835-8
  9. ANSI ANS 51.1: Nuclear Safety Criteria for the Design of Stationary Pressurized Water Reactor Plants, 1983.

See above:

Nuclear Safety