Reactor type choice for nuclear co-generation plant

The base of reactor type choice is whether it will meet the above-mentioned design objectives, technology reality and feasibility and users requirements’ or not

Pressurized water reactors (PWR), boiling water reactors (BWR) and high temperature gas-cooled reactors (HTGR) can all be used as the co-generation plant Comparing with the other types of reactors, for PWR there is a lot of experience in experiment, research, design, manufacture, installation and operation in China.

The steam supply parameters are also the base of reactor type choice. According to the steam parameters which a few large Chinese technological process users need at present, the majority is steam in the middle or in low pressure. From an application of view, PWR and BWR can all meet users’ requirements. The primary circuit pressure of a BWR is usually 6.86MPa. Its core outlet temperature is 285 *c, while usually the core outlet temperature of a PWR can reach 310-325 which can produce medium pressure steam in the third circuit The PWR has a larger application range than the BWR.

In summary, a PWR should be chosen as the nuclear co-generation plant in China, and the steam supply capacity is usually no more than lOOOt/h, so the single-reactor thermal power will not be more than 600MW. A double-reactor in a plant would be better suited to our conditions in which heat and electricity are supplied at the same time and how much the electricity will be produced is based on how much the steam is consumed.

image015

Figure 1 Main System Diagram of Nuclear Thermal Power Plant

 

Подпись: 1. reootor 2. steam generator З.ошіл coolant pump 4. pressurizer 5. aafety bjectlea teak 6. гоііоґ tank 7. volume control tank 0.charging pump 9.rosin bod 1 O.contnlnmont aunip Подпись:11 «residual heat removal pump 12.s&fety lnjootlon ршпр 1 3«spray pump 14.refueling water tank 15«high pressure turbine l6.1ow proesure turbine

17.moisture separator and reheat 10.condenser

19. hydrogen Ion oxchangor

20. ulxod bod

Я..uliod hod 32.ілпк. lip „„tor for third circuit

M. tn boron reevelo svatom

 

image018

OJ

00

 

image019

Figure 2 Small Sized Nuclear Co-generation Plant Thermal-hydraulic System Flow Diagram

 

image020image021
A—A •

I

D direction vie*

J. ГіііІіі |>uoip

і Z. reactor core 1 reactor vesseJ

4. heat eicbiarer

5. CKOH ‘

6. second side taler inlet

7. second side tiler outlet