Understanding Nuclear Reactors: Clarifications Needed

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Discussion Overview

The discussion revolves around clarifications needed regarding the operation and characteristics of nuclear reactors, specifically focusing on the temperature ranges during controlled fission of U-235, the behavior of coolant, and the critical mass of U-235. Participants explore theoretical and practical aspects of nuclear reactor design and function.

Discussion Character

  • Exploratory
  • Technical explanation
  • Debate/contested

Main Points Raised

  • Some participants inquire about the temperature produced during a controlled chain reaction in a nuclear reactor, noting that while uncontrolled reactions can reach millions of degrees Celsius, controlled reactions should produce lower temperatures, potentially in the range of a few thousand degrees.
  • It is mentioned that the boiling point of the coolant, such as pressurized heavy water, is around 300 degrees Celsius, raising questions about how the water remains liquid and effectively conducts heat to the heat exchanger.
  • One participant states that the average fuel temperature for a Pressurized Water Reactor (PWR) is around 1100°F, and explains that the water does not boil due to high pressure (2250 PSI) which raises the saturation temperature to about 650°F.
  • Another participant discusses the concept of controlled fission, emphasizing that the power level is managed by balancing the reaction rate with the coolant flow rate to maintain a constant temperature range.
  • There are discussions about the critical mass and size of U-235, with participants noting that different textbooks provide varying values, which may depend on factors such as enrichment, geometry, and neutron energy spectrum.
  • Some participants mention that nuclear boiling can occur in specific channels of a PWR core, but bulk boiling is not typical, contrasting with Boiling Water Reactors (BWR).
  • One participant humorously suggests that a small reactor could be a sphere of Californium-251, but raises concerns about the heat generated from decay potentially causing it to melt.

Areas of Agreement / Disagreement

Participants express varying views on the temperature ranges and behaviors of coolants in nuclear reactors, with no consensus reached on the exact critical mass of U-235 or the specifics of reactor operation under different conditions.

Contextual Notes

Participants note that the critical mass and size of U-235 depend on multiple factors, including enrichment and geometry, which may explain the discrepancies found in different sources. Additionally, the discussion highlights the complexity of thermal dynamics in nuclear reactors, which may not be fully resolved within the thread.

ananthu
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Regarding nuclear reactor I need some clarifiications;

1. During fisssioin of U-235 it is said that the temperature raises to several million degree celsius (in uncontrolled chain reation). But what will be temperature produced when a controlled chain reaction takes place inside a nuclear reactor? In the case of a coolant such as a pressurised heavy water, its boiling point is only around 300 degree celcicus. Even if the temperature inside a reactors will not be to such an extent of several million degrees as in the case of atom bomb, definitely it will touch a few thousands in the reactor. Then how is that the water remains without boiling in the primary loop and conducts heat to the heat exchanger? What wiil be the temperature range inside a reactor? How is achieved?

2. What is the exact critical mass and size for U-235? Different values are given in different textbooks?
 
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The temperature in the reactor is carefully controlled. Depending on the reactor, the temperatures range from few hundred to few thousand degrees. The rate of the reaction determines the rate at which heat is produced. If all heat produced is carried away by the coolant, the temperature doesn't increase. And the rate of the reaction can be adjusted by adjusting positions of fuel and moderators.
 
Well, hope you know that the end function of a standard controlled nuclear reactor plant IS to produce steam from water to drive turbines connected to a generator.
 
ananthu said:
Regarding nuclear reactor I need some clarifiications;

1. During fisssioin of U-235 it is said that the temperature raises to several million degree celsius (in uncontrolled chain reation). But what will be temperature produced when a controlled chain reaction takes place inside a nuclear reactor? In the case of a coolant such as a pressurised heavy water, its boiling point is only around 300 degree celcicus. Even if the temperature inside a reactors will not be to such an extent of several million degrees as in the case of atom bomb, definitely it will touch a few thousands in the reactor. Then how is that the water remains without boiling in the primary loop and conducts heat to the heat exchanger? What wiil be the temperature range inside a reactor? How is achieved?

2. What is the exact critical mass and size for U-235? Different values are given in different textbooks?

The average fuel temperature for a PWR is around 1100 F. The surface temperature of the fuel rods is lower due to the poor thermal conductivity of the fuel pellets. In a PWR, the water does not boil because it is at 2250 PSI, where the saturation temperature is ~650 F.

The critical mass and size depends on whether it is bare or reflected, and also depends on the temperature and density of the material. That may be why you find different figures.
 
ananthu said:
Regarding nuclear reactor I need some clarifiications;

1. During fission of U-235 it is said that the temperature raises to several million degree celsius (in uncontrolled chain reation). But what will be temperature produced when a controlled chain reaction takes place inside a nuclear reactor? In the case of a coolant such as a pressurised heavy water, its boiling point is only around 300 degree celcicus. Even if the temperature inside a reactors will not be to such an extent of several million degrees as in the case of atom bomb, definitely it will touch a few thousands in the reactor. Then how is that the water remains without boiling in the primary loop and conducts heat to the heat exchanger? What wiil be the temperature range inside a reactor? How is achieved?
Nuclear reactors are 'controlled' - by law and by the physics of the process. Uncontrolled reactors are forbidden, and highly undesirable.

This fission itself produces temperatures on the order of 100 million K, but there are only ~1013 fissions going on in 1022 atoms, so the energy of fission is diluted in the surrounding fuel matrix. The power level is controlled and balanced against the flow rate of the coolant to keep the coolant within a constant temperature range.

Nuclear boiling does occur in some of the hottest channels in a PWR core, but bulk boiling does not occur (as is the case in a BWR). The heat is conducted through the ceramic fuel, then through the metal cladding, which keeps the fuel and fission products isolated from the coolant, and then conducted into the coolant via convective heat transfer (and conduction). Different assemblies have different power levels, so some run a bit cooler than others, and the assemblies on the periphery of the core run at about 30-50% of core average power depending on various factors.

2. What is the exact critical mass and size for U-235? Different values are given in different textbooks?
That depends on the enrichment and geometry (including whether or not it is reflected), and neutron energy spectrum. The simplest (and smallest) would be a sphere of pure U-235.
 
Astronuc said:
Nuclear reactors are 'controlled' - by law and by the physics of the process. Uncontrolled reactors are forbidden, and highly undesirable.

This fission itself produces temperatures on the order of 100 million K, but there are only ~1013 fissions going on in 1022 atoms, so the energy of fission is diluted in the surrounding fuel matrix. The power level is controlled and balanced against the flow rate of the coolant to keep the coolant within a constant temperature range.

Nuclear boiling does occur in some of the hottest channels in a PWR core, but bulk boiling does not occur (as is the case in a BWR). The heat is conducted through the ceramic fuel, then through the metal cladding, which keeps the fuel and fission products isolated from the coolant, and then conducted into the coolant via convective heat transfer (and conduction). Different assemblies have different power levels, so some run a bit cooler than others, and the assemblies on the periphery of the core run at about 30-50% of core average power depending on various factors.

That depends on the enrichment and geometry (including whether or not it is reflected), and neutron energy spectrum. The simplest (and smallest) would be a sphere of pure U-235.

Actually I think the smallest possible reactor would be a sphere of pure Cf-251 reflected with beryllium :biggrin:

Although on second thought, a 4 kg sphere of Cf-251 would probably produce so much heat from decay that it would melt itself. :-p
 
Just imagine how much 4kg of Cf-251 would cost.

And someone didn't specify whether or not they want a prompt critical system or if they were thinking about delayed neutrons or moderated neutrons.

webelements said:
Californium is a radioactive rare Earth metal named after the state of California and the University of California (USA). Californium-252 is a strong neutron emitter and one microgram emits 170 million neutrons per minute, making it a biological hazard. It has a few specialised uses but only a few of its compounds are known.
Actually, Cf-252 is used a primary neutron source in commercial nuclear reactors.
 

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