NUC-410 · Lesson 10 of 12 · 20 min

Chernobyl

Dr. Rohan Desai, the reactor physicist, leads the Chernobyl session because the accident cannot be understood without reactivity feedback. "Every light water reactor TVA operates has strong negative feedback when the coolant boils," he tells Hana. "Lose water and you lose moderation, so power falls. The RBMK at Chernobyl, in the state it was in that night, did the opposite, and its shutdown system made things worse in its first seconds. Read INSAG-7 before we start. It is the IAEA's revised account, and it is much fairer to the operators than the first one."

The RBMK reactor

Chernobyl Unit 4, near Pripyat in what was then the Ukrainian Soviet Socialist Republic, was an RBMK-1000, a graphite-moderated, light-water-cooled, channel-type reactor of 3 200 megawatts thermal. The core was a large cylinder of graphite blocks about 12 meters across and 7 meters high, pierced by about 1 660 vertical fuel channels. Ordinary water flowed up through the channels and boiled, and the steam went directly to the turbines. The reactor had no containment building of the kind used in Western light water reactors; parts of the primary system were enclosed in compartments designed for limited pipe breaks.

Because graphite does the moderating, the water in the channels acts mainly as an absorber of neutrons. When the water boils and its density falls, fewer neutrons are absorbed and reactivity rises. This gives a positive void coefficient. In the RBMK, the size of the void coefficient depended strongly on the state of the core: it was most positive at low power, with low enrichment fuel at high burnup and with few control rods inserted. At normal full power, the negative fuel temperature coefficient dominated and the overall power coefficient was negative; at low power it could become positive.

A line chart of relative power against time for three illustrative void coefficients. With a negative coefficient, power rises slightly and levels off. With a zero coefficient, it rises a little more. With a positive coefficient, power accelerates sharply upward within a few seconds.
Illustrative power response to a reduction in coolant flow for negative, zero and positive void feedback. The curves come from the toy model below, not from an RBMK model.
A toy model of void feedback: a loss of flow raises the void fraction, which changes reactivity according to the void coefficient. Values are illustrative.
# Point-kinetics toy with void feedback (illustrative only; not RBMK design data).
# One delayed group. A void coefficient alpha_v adds reactivity as power raises voiding.
beta, lam, Lgen = 0.0050, 0.08, 1e-3
def run(alpha_v, rho_ext=0.0005, t_end=20.0, dt=1e-3):
    n, c = 1.0, beta / (lam * Lgen)
    void = 0.0; t = 0.0
    while t < t_end:
        void += (0.3 * (n - 1.0) - void) * dt / 1.0      # void follows power with a 1 s lag
        rho = rho_ext + alpha_v * void
        dn = ((rho - beta) / Lgen * n + lam * c) * dt
        dc = (beta / Lgen * n - lam * c) * dt
        n += dn; c += dc; t += dt
        if n > 100: return t, n
    return t_end, n
for a in (-0.01, 0.0, +0.01):
    t, n = run(a)
    print(f"void coefficient {a:+.2f} per unit void: relative power {n:7.2f} at t = {t:5.2f} s")
Output
void coefficient -0.01 per unit void: relative power    1.12 at t = 20.00 s
void coefficient +0.00 per unit void: relative power    1.32 at t = 20.00 s
void coefficient +0.01 per unit void: relative power  100.06 at t =  6.97 s

The toy model shows why the sign of the feedback matters. With negative void feedback, an increase in boiling reduces power and the plant settles to a new state. With positive feedback, an increase in boiling raises power, which increases boiling further, and once the reactivity exceeds the delayed neutron fraction the reactor becomes prompt critical and power rises in a fraction of a second. Real reactors also have fuel temperature feedback, which is negative in all designs and limits the power excursion, but in the Chernobyl accident it could not act fast enough to prevent the destruction of the core.

The shutdown system design

The RBMK control rods had a further design weakness. Each rod had a graphite displacer attached below its absorber section. When a fully withdrawn rod began to move into the core, the graphite displaced water from the lower part of the channel before the absorber arrived. Since water absorbs neutrons and graphite moderates them, this first motion added reactivity in the lower core. In addition, the rods moved slowly, taking about 18 seconds to insert fully. In most conditions this positive scram effect was small, but in a core with a flattened axial power distribution, few rods inserted and a positive void coefficient, it could be enough to start an excursion. The effect had been seen at the Ignalina plant in 1983 but the information had not been effectively acted on.

The test and the accident

The accident occurred early on 26 April 1986, during a test of whether the turbine generator, coasting down after the steam supply was cut off, could supply enough electricity to run cooling pumps until the diesel generators started. The test had been scheduled during a planned shutdown. It was delayed for many hours at the request of the grid controller, so it was carried out by a night shift that had not prepared for it, with the reactor operating at reduced power for an extended time, which built up xenon poisoning in the core.

When the power was reduced further for the test, it fell much lower than intended, to around 30 megawatts thermal, because of the xenon and control difficulties. The operators withdrew many control rods to raise the power, which reached about 200 megawatts, well below the 700 to 1 000 megawatts intended in the test program. The number of rods remaining in the core was far below the minimum then specified in operating rules, although the importance of this limit was not adequately explained in the documentation. Additional main circulation pumps had been started as part of the test, so the coolant flow was high and the water entering the core was close to boiling. Several automatic trips had been disabled to allow the test to proceed or to be repeated.

At 1:23:04 the test began and the turbine stop valves were closed. As the turbine coasted down, the pumps it supplied slowed, the flow through the core fell, and boiling increased. In this state, with a large positive void coefficient, power began to rise. About 36 seconds after the start of the test, the emergency protection button was pressed and the control rods began to move in. The graphite displacers added reactivity at the bottom of the core, and within seconds the power rose to many times full power. The fuel fragmented, the channels ruptured, and steam explosions lifted the 1 000-metric ton upper plate of the reactor and destroyed the building. A second explosion followed seconds later. Hot fragments of fuel and graphite were scattered and started fires on the roofs, and the graphite in the open core burned for days.

Contributing factors at Chernobyl, as described in INSAG-7.
FactorDescription
Positive void coefficientLarge in the low-power, low-rod state; drove the excursion
Positive scram effectGraphite displacers added reactivity in the first seconds of rod insertion
Slow shutdown systemAbout 18 seconds for full insertion
Operating stateLow power, xenon poisoning, few rods inserted, high flow near boiling
Disabled protectionSome automatic trips had been bypassed for the test
Test preparationProgram reviewed inadequately and carried out by an unprepared shift after delays
Lack of containmentNo full containment to retain fission products
Safety cultureWeak communication of design limits and operating experience; production pressure

INSAG-1 and INSAG-7

The first international account, INSAG-1, published by the International Nuclear Safety Advisory Group in 1986 on the basis of Soviet information presented in Vienna, placed most of the blame on violations of operating procedures by the operators. INSAG-7, published in 1992 after new information became available, revised that view. It concluded that while operator actions contributed, the design deficiencies of the reactor, particularly the positive void coefficient and the control rod design, were major causes, and that some of the actions described as violations were not prohibited by the rules in force or by the documents available to the operators. INSAG-7 also concluded that the accident reflected a deficient safety culture throughout the Soviet nuclear power program, from design and regulation to operation, and the term safety culture, introduced in INSAG-1, became central to the industry.

Consequences

Chernobyl is the most serious accident in the history of nuclear power and is rated level 7, a major accident, on the International Nuclear and Radiological Event Scale. Two plant workers died on the night of the accident, and 28 of the emergency workers and plant staff with acute radiation syndrome died within a few months. Large amounts of iodine-131, cesium-137 and other radionuclides were released over about ten days, contaminating large areas of Ukraine, Belarus and Russia and, at lower levels, much of Europe. About 116 000 people were evacuated in 1986, and later relocations brought the total to more than 300 000.

The most clearly documented long-term health effect is an increase in thyroid cancer among people who were children or adolescents at the time, mainly from drinking milk contaminated with iodine-131 in the first weeks before protective measures were effective. Thousands of cases have been diagnosed, although the great majority were treated successfully. The UN Scientific Committee on the Effects of Atomic Radiation and the Chernobyl Forum have reported that other health effects among the general public are hard to detect against the background of other causes, while psychological and social effects of relocation and uncertainty have been severe. A shelter, often called the sarcophagus, was built over the ruined unit in 1986, and the New Safe Confinement, an arch-shaped structure, was slid over it in 2016.

What changed

Remaining RBMK reactors were modified to reduce the void coefficient, by increasing fuel enrichment, adding fixed absorbers and requiring more control rods to remain in the core, and the control rods and shutdown system were redesigned to insert faster and without the positive scram effect. Internationally, the accident led to new conventions: the Convention on Early Notification of a Nuclear Accident and the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency in 1986, and later the Convention on Nuclear Safety, which entered into force in 1996 and requires periodic peer review of national safety programs. Operators formed the World Association of Nuclear Operators, WANO, in 1989 to share operating experience and conduct peer reviews worldwide.

For US light water reactors, which have negative void and moderator temperature coefficients at operating conditions and large containments, the NRC concluded that the specific RBMK mechanisms did not apply, and its review, NUREG-1251, examined lessons for areas such as control of tests, administrative controls and emergency planning. The safety culture lessons, however, applied everywhere, and US utilities, including TVA, strengthened the control of special tests and infrequently performed evolutions.

Worked problem

Prompt criticality

The delayed neutron fraction of uranium-235 fuel is about 0.0065. If the void coefficient in a given core state is +4 × 10⁻⁴ per percent void, how large an increase in average void would add reactivity equal to the delayed neutron fraction?

Show solution
  1. Reactivity added: ρ = 4 × 10⁻⁴ × Δα, with Δα in percent void.
  2. Set ρ = β = 0.0065: Δα = 0.0065/(4 × 10⁻⁴) ≈ 16 percent.
  3. Beyond this, the reactor is prompt critical and power rises on the timescale of the prompt neutron lifetime.

Answer: An increase of about 16 percentage points in average void would make the reactor prompt critical in this illustrative case.

\[\rho_{void} = \alpha_V\,\Delta V, \qquad \rho \ge \beta \;\Rightarrow\; \text{prompt critical}\]

The emergency response

The response to the accident was carried out under extreme conditions. Firefighters from the plant and from Pripyat climbed onto the roofs of the turbine hall and the adjacent unit to put out fires that threatened unit 3, receiving very high doses. Over the following days, helicopters dropped thousands of metric tons of sand, clay, lead, boron carbide and dolomite onto the ruined reactor in an attempt to smother the burning graphite and reduce releases. Pripyat, a town of about 50 000 people, was evacuated on 27 April, about 36 hours after the accident, and the evacuation of a 30-kilometer zone followed in early May. Hundreds of thousands of workers, often called liquidators, took part in the cleanup over the following years.

The delay in informing the public, both in the Soviet Union and internationally, was itself a lesson. The release was first detected abroad by radiation monitors at a nuclear plant in Sweden. The conventions on early notification and assistance that followed were designed so that countries would be informed promptly and could request help.

Common mistakes

  • MistakeChernobyl was caused only by operator violations.

    InsteadINSAG-7 identified major design deficiencies as well as operator actions and a weak safety culture.

  • MistakeThe explosion was a nuclear explosion like a weapon.

    InsteadIt was a power excursion followed by steam explosions that destroyed the reactor.

  • MistakeAny reactor could behave like the RBMK.

    InsteadLight water reactors have negative void feedback; CANDU limits void reactivity and has two fast shutdown systems.

Summary and key terms

  • Chernobyl Unit 4 was an RBMK with a positive void coefficient, especially at low power with few rods inserted.
  • On 26 April 1986, during a turbine rundown test at low power, a power excursion destroyed the reactor.
  • The graphite displacers on the control rods added reactivity in the first seconds of the scram.
  • INSAG-7 revised INSAG-1, finding design deficiencies and a deficient safety culture as well as operator actions.
  • The accident led to RBMK modifications, international conventions, WANO and the concept of safety culture.
RBMK
A Soviet graphite-moderated, light-water-cooled, channel-type reactor.
Void coefficient
The change in reactivity per unit change in coolant void fraction.
Prompt critical
A state in which the chain reaction is sustained by prompt neutrons alone, so power rises very rapidly.
Positive scram effect
An initial reactivity increase caused by control rod insertion.
INSAG-7
The 1992 IAEA safety advisory group report revising the account of the Chernobyl accident.
Xenon poisoning
Absorption of neutrons by xenon-135 that builds up after a power reduction.

Practice problems

Work each problem on paper first, then reveal the answer to check.

  1. Why does boiling raise reactivity in an RBMK?

    Show answer

    Water mainly absorbs neutrons there, so less water means less absorption.

  2. What did the graphite displacers do during the scram?

    Show answer

    They displaced water at the bottom of the channels, adding reactivity.

  3. What was the test intended to show?

    Show answer

    Whether the coasting turbine could power cooling pumps until the diesels started.

  4. How did INSAG-7 differ from INSAG-1?

    Show answer

    It gave greater weight to design deficiencies and safety culture.

  5. What is the INES level of the accident?

    Show answer

    Level 7.

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