MARC details
| 000 -LEADER |
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| fixed length control field |
04627cam a2200457Mi 4500 |
| 001 - CONTROL NUMBER |
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| control field |
on1319213923 |
| 003 - CONTROL NUMBER IDENTIFIER |
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| control field |
OCoLC |
| 005 - DATE AND TIME OF LATEST TRANSACTION |
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| control field |
20240726104852.0 |
| 008 - FIXED-LENGTH DATA ELEMENTS--GENERAL INFORMATION |
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| fixed length control field |
221015s2020 xx o ||| 0 eng d |
| 040 ## - CATALOGING SOURCE |
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| Original cataloging agency |
EBLCP |
| Language of cataloging |
eng |
| Description conventions |
rda |
| Transcribing agency |
EBLCP |
| Modifying agency |
NT |
| -- |
EBLCP |
| -- |
OCLCQ |
| -- |
NT |
| 020 ## - INTERNATIONAL STANDARD BOOK NUMBER |
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| International Standard Book Number |
9201064225 |
| 020 ## - INTERNATIONAL STANDARD BOOK NUMBER |
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| International Standard Book Number |
9789201064226 |
| Qualifying information |
|
| 050 04 - LIBRARY OF CONGRESS CALL NUMBER |
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| Classification number |
TK9212 |
| Item number |
.D475 2020 |
| 049 ## - LOCAL HOLDINGS (OCLC) |
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| Holding library |
MAIN |
| 100 1# - MAIN ENTRY--PERSONAL NAME |
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| Personal name |
IAEA. |
| Relator term |
Author |
| 245 10 - TITLE STATEMENT |
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| Title |
Design of the Reactor Coolant System and Associated Systems for Nuclear Power Plants |
| Remainder of title |
Specific Safety Guide. |
| Statement of responsibility, etc. |
|
| 260 ## - PUBLICATION, DISTRIBUTION, ETC. |
|---|
| Place of publication, distribution, etc. |
Havertown : |
| Name of publisher, distributor, etc. |
International Atomic Energy Agency, |
| Date of publication, distribution, etc. |
(c)2020. |
| 300 ## - PHYSICAL DESCRIPTION |
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| Extent |
1 online resource (102 pages). |
| 336 ## - CONTENT TYPE |
|---|
| Content type term |
text |
| Content type code |
txt |
| Source |
rdacontent |
| 337 ## - MEDIA TYPE |
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| Media type term |
computer |
| Media type code |
c |
| Source |
rdamedia |
| 338 ## - CARRIER TYPE |
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| Carrier type term |
online resource |
| Carrier type code |
cr |
| Source |
rdacarrier |
| 347 ## - DIGITAL FILE CHARACTERISTICS |
|---|
| File type |
data file |
| Source |
rda |
| 490 1# - SERIES STATEMENT |
|---|
| Series statement |
IAEA Safety Standards Ser. ; |
| Volume # |
v.SSG-56 |
| 500 ## - GENERAL NOTE |
|---|
| General note |
Description based upon print version of record. |
| 504 ## - BIBLIOGRAPHY, ETC. NOTE |
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| Bibliography, etc. note |
Includes bibliographies and index. |
| 505 00 - FORMATTED CONTENTS NOTE |
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| Formatted contents note |
Intro -- |
| Title |
1. INTRODUCTION -- |
| -- |
Background -- |
| -- |
Objective -- |
| -- |
Scope -- |
| -- |
Structure -- |
| -- |
2. Extent of the reactor coolant system and associated systems -- |
| -- |
Reactor coolant system -- |
| -- |
Systems for heat removal in shutdown conditions -- |
| -- |
Systems for coolant inventory control in operational states -- |
| -- |
Systems for control of core reactivity in operational states -- |
| -- |
Systems for core cooling and residual heat removal in accident conditions -- |
| -- |
Systems for control of core reactivity in accident conditions -- |
| -- |
Ultimate heat sink and residual heat transfer systems in all plant states |
| 505 00 - FORMATTED CONTENTS NOTE |
|---|
| Formatted contents note |
3. DESIGN BASIS OF THE REACTOR COOLANT SYSTEM AND ASSOCIATED SYSTEMS -- |
| Title |
General -- |
| -- |
Safety functions -- |
| -- |
Postulated initiating events -- |
| -- |
Internal hazards -- |
| -- |
External hazards -- |
| -- |
Accident conditions -- |
| -- |
Design basis accidents -- |
| -- |
Design extension conditions without significant fuel degradation -- |
| -- |
Design limits and acceptance criteria -- |
| -- |
Reliability -- |
| -- |
Systems designed to cope with design basis accidents -- |
| -- |
Safety features for design extension conditions without significant fuel degradation -- |
| -- |
Defence in depth -- |
| -- |
Safety classification -- |
| -- |
Environmental qualification of items important to safety |
| 505 00 - FORMATTED CONTENTS NOTE |
|---|
| Formatted contents note |
Loads and load combinations -- |
| Title |
Materials -- |
| -- |
Materials in contact with radioactive fluids -- |
| -- |
Materials exposed to high neutron flux -- |
| -- |
Manufacturing and installation -- |
| -- |
Calibration, testing, maintenance, repair, replacement, inspection and monitoring -- |
| -- |
Pre-service and in-service inspection of the reactor coolant system -- |
| -- |
Inspection of steam generators -- |
| -- |
Overpressure protection -- |
| -- |
Layout -- |
| -- |
Radiation protection -- |
| -- |
Combustible gas accumulation in normal operation -- |
| -- |
Venting and draining -- |
| -- |
Interfaces between the reactor coolant system and associated systems -- |
| -- |
Containment isolation |
| 505 00 - FORMATTED CONTENTS NOTE |
|---|
| Formatted contents note |
Instrumentation -- |
| Title |
Multiple units at a site -- |
| -- |
Codes and standards -- |
| -- |
Use of probabilistic analyses in design -- |
| -- |
4. ULTIMATE HEAT SINK AND RESIDUAL HEAT TRANSFER SYSTEMS -- |
| -- |
Ultimate heat sink -- |
| -- |
Residual heat transfer systems -- |
| -- |
Residual heat transfer in operational states -- |
| -- |
Residual heat transfer for design basis accidents -- |
| -- |
Residual heat transfer for design extension conditions -- |
| -- |
5. SPECIFIC CONSIDERATIONS IN DESIGN OF THE REACTOR COOLANT SYSTEM -- |
| -- |
Structural design -- |
| -- |
Design basis loads and load combinations -- |
| -- |
Control of cooling conditions in operational states |
| 505 00 - FORMATTED CONTENTS NOTE |
|---|
| Formatted contents note |
Pressure control and overpressure protection -- |
| Title |
Isolation of the reactor coolant pressure boundary -- |
| -- |
Postulated initiating events -- |
| -- |
Internal hazards -- |
| -- |
External hazards -- |
| -- |
Layout -- |
| -- |
Design limits -- |
| -- |
Safety classification -- |
| -- |
Environmental qualification -- |
| -- |
Pressure tests -- |
| -- |
Venting -- |
| -- |
For pressurized water reactors -- |
| -- |
For boiling water reactors -- |
| -- |
For pressurized heavy water reactors -- |
| -- |
Specific design aspects -- |
| -- |
Reactor pressure vessel -- |
| -- |
Reactor pressure vessel internals (for PWRs and BWRs) -- |
| -- |
Fuel channel assemblies (for PHWRs) |
| 500 ## - GENERAL NOTE |
|---|
| General note |
Reactor coolant pumps (for PWRs and PHWRs) and reactor recirculation pumps (for BWRs) |
| 530 ## - COPYRIGHT INFORMATION: |
|---|
| COPYRIGHT INFORMATION |
COPYRIGHT NOT covered - Click this link to request copyright permission: |
| Uniform Resource Identifier |
<a href="b">b</a> |
| 650 #0 - SUBJECT ADDED ENTRY--TOPICAL TERM |
|---|
| Topical term or geographic name entry element |
Nuclear power plants |
| General subdivision |
Design and construction. |
| 650 #0 - SUBJECT ADDED ENTRY--TOPICAL TERM |
|---|
| Topical term or geographic name entry element |
Nuclear reactors |
| General subdivision |
Cooling. |
| 650 #0 - SUBJECT ADDED ENTRY--TOPICAL TERM |
|---|
| Topical term or geographic name entry element |
Nuclear power plants |
| General subdivision |
Safety measures. |
| 655 #1 - INDEX TERM--GENRE/FORM |
|---|
| Genre/form data or focus term |
Electronic Books. |
| 856 40 - ELECTRONIC LOCATION AND ACCESS |
|---|
| -- |
Click to access digital title | log in using your CIU ID number and my.ciu.edu password. |
| Uniform Resource Identifier |
<a href="httpss://search.ebscohost.com/login.aspx?direct=true&scope=site&db=nlebk&db=nlabk&AN=3282288&site=eds-live&custid=s3260518">httpss://search.ebscohost.com/login.aspx?direct=true&scope=site&db=nlebk&db=nlabk&AN=3282288&site=eds-live&custid=s3260518</a> |
| 942 ## - ADDED ENTRY ELEMENTS (KOHA) |
|---|
| Koha item type |
Online Book (LOGIN USING YOUR MY CIU LOGIN AND PASSWORD) |
| DONATED BY: |
|
| VENDOR |
EBSCO |
| Classification part |
TK |
| PUBLICATION YEAR |
2020 |
| LOCATION |
ONLINE |
| REQUESTED BY: |
|
| -- |
|
| -- |
NFIC |
| Source of classification or shelving scheme |
|
| 994 ## - |
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| -- |
92 |
| -- |
NT |
| 902 ## - LOCAL DATA ELEMENT B, LDB (RLIN) |
|---|
| a |
1 |
| b |
Cynthia Snell |
| c |
1 |
| d |
Cynthia Snell |