Download e-book for iPad: Ageing of Nucl. Powerplant Compnts. - BWR Pressure Vessel by

Read Online or Download Ageing of Nucl. Powerplant Compnts. - BWR Pressure Vessel Internals (IAEA TECDOC-1471) PDF

Similar nonfiction_6 books

Elliptic Partial Differential Equations of Second Order, 2nd by David Gilbarg, Neil S. Trudinger PDF

Bankruptcy 1. advent half I: Linear Equations bankruptcy 2. Laplace's Equation 2. 1 The suggest price Inequalities 2. 2 greatest and minimal precept 2. three The Harnack Inequality 2. four Green's illustration 2. five The Poisson necessary 2. 6 Convergence Theorems 2. 7 inside Estimates of Derivatives 2. eight The Dirichlet challenge; the tactic of Subharmonic features 2.

Extra info for Ageing of Nucl. Powerplant Compnts. - BWR Pressure Vessel Internals (IAEA TECDOC-1471)

Example text

4550 (core shroud region) and the EPRI Guideline were taken into account for this revision. However there are some discrepancies between this guideline and the EPRI Guideline. e. use of stabilized stainless steels. 44 TABLE 4-2a EPRI WATER CHEMISTRY GUIDELINES REACTOR WATER –NWC- POWER OPERATION (>10% Power) a Note: This table applies to site specific target components exposed to NWC environments or not protected to –230 mV(SHE) by HWC. 0 Chloride (ppb) Daily b >5 >20 >100 Sulfate (ppb) Daily b >5 >20 >100 Zinc (ppb) c --- Diagnostic Parameter Frequency of Measurement Oxygen (ppb) Continuously Silica (ppb) --- Co, Zn (Zinc plants only) d 60 65 Iron (ppb) Weekly Sample Monthly Comments --b --(e) Notes: (a) If HWC is not incorporated into the station chemistry program, an engineering evaluation should be performed to support the decision using an appropriate assessment methodology.

For German BWRs, the VGB Guideline for the Water in Nuclear Power Plants with Light Water Reactors specifies the qualitative feedwater and reactor water requirements. This guideline was revised in 1996. Table 4-3a to c show the operating values of the revised VGB Guideline. 4550 (core shroud region) and the EPRI Guideline were taken into account for this revision. However there are some discrepancies between this guideline and the EPRI Guideline. e. use of stabilized stainless steels. 44 TABLE 4-2a EPRI WATER CHEMISTRY GUIDELINES REACTOR WATER –NWC- POWER OPERATION (>10% Power) a Note: This table applies to site specific target components exposed to NWC environments or not protected to –230 mV(SHE) by HWC.

Plants, which have been uprated, may experience FIV at the new operating conditions. 2. Significance of fatigue Fatigue life estimates include both crack initiation and crack propagation. Crack initiation is estimated by determining the fatigue usage at a specific location that results from either actual or design basis cyclic loads. Time to initiation can be predicted only if the sequence of the applied loads and recurrence frequency is well known. Such estimates are uncertain if the cyclic loading is random.

Download PDF sample

Ageing of Nucl. Powerplant Compnts. - BWR Pressure Vessel Internals (IAEA TECDOC-1471)


by John
4.4

Rated 4.44 of 5 – based on 29 votes