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ASME PTC 32.1

1969 Edition, 1969

Complete Document

Nuclear Steam Supply Systems

Includes all amendments and changes through Reaffirmation Notice , 1992


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Product Details:

  • Revision: 1969 Edition, 1969
  • Published Date: January 1992
  • Status: Not Active, See comments below
  • Document Language: English
  • Published By: ASME International (ASME)
  • Page Count: 35
  • ANSI Approved: Yes
  • DoD Adopted: No

Description / Abstract:

OBJECT AND SCOPE

The purpose of this Code is to establish procedures for conducting tests to determine the thermal performance of a nuclear steam supply system as a unit. These tests include capacity, reactor power level, efficiency, and other related operating characteristics such a s steam pressure, moisture content, and solids in the steam. (See Section 4.)

A determination of any or all of the performance items specified above may be necessary for purposes such as:

Checking the actual performance against guarantee.

Comparing these items with some standard of performance.

Comparing performance at different operating conditions.

Checking performance after new reactor fuel is loaded.

Determining the effects of changes to equipment.

Periodic verification of the means employed to monitor reactor power level.

The rules and instructions given in this Code apply to the equipment defined in the introduction. Testing of auxiliary apparatus shall be governed by the Performance Test Code applying specifically to the auxiliary apparatus in question.

Since there is no accurate, direct method of measuring the energy released by the nuclear fuel, the only method used for calculating the energy balance is the direct measurement of the energy output, losses and credits. This is referred to hereinafter as the energy loss method.

The output is defined as the energy absorbed by the working fluid or fluids within the envelope boundary, The working fluid is the steam and water substance through which means the nuclear steam supply system delivers energy.

The input is defined as the energy released by the nuclear fuel plus energy credits added to the working fluid or fluids, air, gas, and other fluid circuits that cross the envelope boundary, as shown in Figure for pressurized water reactors (PWR) and in Figure 3 for boiling water reactors (BWR). The envelope boundary encompasses the equipment to be included in the designation "nuclear steam supply system." The input is equal to the output plus losses.

Energy credits are defined as those amounts of energy added to the envelope of the nuclear steam supply system other than the nuclear energy released by the fuel. These credits include quantities such as pumping energy.

Losses are defined as energy lost from the envelope of the nuclear steam supply system.

For a better understanding of the relationships between input, output, credits, and losses, refer to Figures 2 (PWR) or 4 (BWR).

The capacity of a nuclear steam supply system is defined as the actual evaporation rate of steam in pounds per hour delivered at specified conditions of the working fluid.

The reactor power level is defined as the rate of energy release in the reactor core in units of megawatts.

The efficiency of a nuclear steam supply system, as determined within the scope of this Code, is defined as the ratio of energy absorbed by the working fluid or fluids to energy input as defined in Par. 1.04.2. This definition disregards the energy supplied to the auxiliary apparatus external to the envelope. (See Figures 1 and 3.)

Efficiency is expressed by the following equation:



The determination of data of a research nature or other special data is not covered by this Code.

It is recommended that a report be prepared for each test, giving complete details of the conditions under which the test has been made, including a record of test procedures and all data in a form suitable for demonstrating that the objectives of the test have been attained.