## Fuel Consumption of Conventional Reactor

A typical **nuclear power plant** has an electric-generating capacity of **1000 MWe**. The heat source in the nuclear power plant is a **nuclear reactor**. As is typical in all conventional thermal power stations the heat is used to generate steam which drives a **steam turbine** connected to a generator which produces electricity. The turbines are heat engines and are subject to the efficiency limitations imposed by the **second law of thermodynamics**. In modern nuclear power plants the overall thermodynamic efficiency is about **one-third **(33%), so **3000 MWth** of thermal power from the fission reaction is needed to generate **1000 MWe** of electrical power.

This thermal power is generated in a reactor core, which contains especially the nuclear fuel (fuel assemblies), the moderator and the control rods. The core of the reactor contains all the nuclear fuel assemblies and generates most of the heat (fraction of the heat is generated outside the reactor – e.g. gamma rays energy). The assemblies are exactly placed in the reactor according to a fuel loading pattern.

A typical 1000 MWe (3000 MWth) nuclear core may contain 157 fuel assemblies composed of over **45,000 fuel rods **and some **15 million fuel pellets**. Generally, a common fuel assembly contain energy for approximately **4 years of operation at full power**. Once loaded, fuel stays in the core for 4 years depending on the design of the operating cycle. During these 4 years the reactor core have to be refueled. During refueling, every 12 to 18 months, some of the fuel – usually **one third or one quarter of the core** – is removed to **spent fuel pool**, while the remainder is rearranged to a location in the core better suited to its remaining level of enrichment. The removed fuel (one third or one quarter of the core, i.e. 40 assemblies) has to be replaced by a **fresh fuel assemblies**. It follows, there are about 3-4 fuel batches which differ each other in the fuel burnup.

**The total energy released** in a reactor is **about 210 MeV** per ^{235}U fission, distributed as shown in the table. In a reactor, **the average recoverable energy** per fission is **about 200 MeV**, being the total energy minus the energy of the energy of antineutrinos that are radiated away. This means that **about 3.1****⋅****10**^{10}** fissions per second** are required to produce a thermal power of **1 W**. Since **1 gram** of any fissile material contains about **2.5 x 10**^{21}** nuclei**, the fissioning of 1 gram of fissile material yields **about 1 megawatt-day (MWd)** of heat energy.

## Summary:

**Consumption of a 3000MWth (~1000MWe) reactor (12-months fuel cycle)**

*It is an illustrative example, following data do not correspond to any reactor design.*

- Typical reactor may contain about
**165 tonnes of fuel**(including structural material) - Typical reactor may contain about
**100 tonnes of enriched uranium**(i.e. about 113 tonnes of uranium dioxide). - This fuel is loaded within, for example,
**157 fuel assemblies**composed of over**45,000 fuel rods.** - A common fuel assembly contain energy for approximately
**4 years of operation at full power**. - Therefore about
**one quarter of the core**is yearly removed to**spent fuel pool**(i.e. about 40 fuel assemblies), while the remainder is rearranged to a location in the core better suited to its remaining level of enrichment (see Power Distribution). - The removed fuel (
**spent nuclear fuel**) still contains about**96% of reusable material**(it must be removed due to decreasing**k**of an assembly)._{inf}

**Annual natural uranium consumption**of this reactor is about**250 tonnes of natural uranium**(to produce of about 25 tonnes of enriched uranium).

**Annual enriched uranium consumption**of this reactor is about**25 tonnes of enriched uranium**.

**Annual fissile material consumption**of this reactor is about**1 005 kg**.

**Annual matter consumption**of this reactor is about**1.051 kg**.

- But it corresponds to
**about 3 200 000 tons**of**coal burned in**per year.**coal-fired power plant**

## Uranium 235 consumption in a nuclear reactor

A typical **thermal reactor** contains about **100 tons** of uranium with an average enrichment of **2%** (do not confuse it with the enrichment of the **fresh fuel, **that is about 4%). For the reactor of power of **3000MW _{th}** determine the consumption of

**that must undergo fission each day to provide this thermal power.**

^{235}U**Solution:**

This problem can be solved very simply. The average recoverable energy per ^{235}U fission is about **E**_{r}** = 200.7 MeV/fission**. Since we know that each second we need **3000 MJ** of energy, the required reaction rate can be determined directly as:

Since each atom of ** ^{235}U** has a mass of 235u x 1.66 x 10

^{-27}kg/u = 3.9 x 10

^{-25}kg, the daily consumption of a reactor is:

9.33 x 10^{19} fissions/sec x 3.9 x 10^{-25} kg x 86400 sec/day = **3.14 kg/day**

For comparison, a 1000 MWe coal-fired power plant burns about 10 000 tons (about 10 million kg) of coal per day.

Since a typical fuel cycle takes about 320 days (12 month fuel cycle), the annual fuel consumption is about:

3.14 kg/day x 320 days = **1 005 kg of ^{235}U**

## Fissile material consumption in a nuclear reactor

All commercial light water reactors contains both fissile and fertile materials. For example, most PWRs use low enriched uranium fuel with enrichment of ^{235}**U** up to 5%. Therefore more than 95% of content of fresh fuel is fertile isotope ^{238}**U**.

In fact, during fuel burnup the fertile materials (conversion of ^{238}**U** to fissile ^{239}**Pu** known as **fuel breeding**) partially replace fissile ^{235}**U, **thus in a nuclear reactor more fissile isotopes are involved in power generation. Since the ^{239}Pu fission releases very similar amount of energy, this example can be generalized to:

**Annual consumption is: 1 005 kg of all fissile material involved.**

The **fuel breeding** permits power reactors to operate longer before the amount of fissile material decreases to the point where reactor criticality is no longer manageable.

**The fuel breeding** in the fuel cycle of all commercial light water reactors plays a significant role. In recent years, the commercial power industry has been emphasizing **high-burnup fuels** (up to 60 – 70 GWd/tU), which are typically enriched to higher percentages of ^{235}**U** (up to 5%). As burnup increases, a higher percentage of the total power produced in a reactor is due to the fuel bred inside the reactor.

At a burnup of **30 GWd/tU** (gigawatt-days per metric ton of uranium), about **30%** of the total energy released comes from bred plutonium. At **40 GWd/tU**, that percentage increases to about **forty percent**. This corresponds to a **breeding ratio** for these reactors of about 0.4 to 0.5. That means, about half of the fissile fuel in these reactors is bred there. This effect extends the cycle length for such fuels to sometimes nearly twice what it would be otherwise. **MOX fuel** has a smaller breeding effect than ^{235}**U** fuel and is thus more challenging and slightly less economic to use due to a quicker drop off in reactivity through cycle life.

## Natural uranium consumption in a nuclear reactor

**Natural uranium** refers to uranium with the same isotopic ratio as found in nature. It consists primarily of isotope ^{238}U (99.28%), therefore the atomic mass of uranium element is close to the atomic mass of ^{238}U isotope (238.03u). Natural uranium also consists of two other isotopes: ^{235}U (0.71%) and ^{234}U (0.0054%). The abundance of isotopes in the nature is caused by difference in the half-lifes. All three naturally-occurring isotopes of uranium (^{238}U, ^{235}U and ^{234}U) are unstable. On the other hand these isotopes (except ^{234}U) belong to primordial nuclides, because their half-life is comparable to the age of the Earth (~4.5×10^{9} years for ^{238}U).

Since **natural uranium** contains only 0.71% of fissile isotope ^{235}U and most of current power reactors require enriched uranium, this natural uranium must be enriched. The level of enrichment required depends on specific reactor design (e.g. PWRs and BWRs require 3% – 5% of 235U) and specific requirements of the nuclear power plant operator. Without required enrichment these reactors are not able to initiate and sustain a nuclear chain reaction for such a long period as 12 months (or more).

The enrichment process separates gaseous uranium hexafluoride into two streams, one being enriched to the required level and known as low-enriched uranium, the other stream is progressively depleted in U-235 and is called **‘tails’**, or simply **depleted uranium**. Typically, to produce 1 kg of enriched uranium with 5% of ^{235}U, about 10 kg of natural uranium is required with a byproduct of about 9 kg of depleted uranium. Therefore **annual natural uranium consumption** of 3000MWth reactor is about **250 tonnes of natural uranium** (to produce of about 25 tonnes of enriched uranium).

## Matter consumption in a nuclear reactor

In general, the **nuclear fission** results in the release of **enormous quantities of energy**. This energy comes from the nuclear binding energy which holds nuclei together. The binding energy per nucleon is higher for fission fragments than for uranium nuclei. It was found **the sum of the rest masses of products of fission is measurably smaller than the rest mass of uranium nucleus.**

It is due to the fact during the **nuclear fission** some of the mass of the nucleus gets converted into these huge amounts of energy and thus this mass is removed from the total mass of the original particle, and the mass is missing in the resulting nuclei.

According to the Einstein relationship (**E = mc**** ^{2}**) this binding energy is proportional to this mass difference and it is known as the

**mass defect**.

The annual **mass defect** of a typical 3000MW_{th} reactor can be calculated directly from the Einstein relationship (**E = mc**** ^{2}**) as:

Δm = ΔE/c^{2}

Δm = 3000×10^{6} (W = J/s) x 31.5×10^{6} (seconds in year) / (2.9979 x 10^{8})^{2 }= **1.051 kg**