{"id":80917,"date":"2024-10-17T18:49:22","date_gmt":"2024-10-17T18:49:22","guid":{"rendered":"https:\/\/pdfstandards.shop\/product\/uncategorized\/ieee-n320-1979\/"},"modified":"2024-10-24T19:45:08","modified_gmt":"2024-10-24T19:45:08","slug":"ieee-n320-1979","status":"publish","type":"product","link":"https:\/\/pdfstandards.shop\/product\/publishers\/ieee\/ieee-n320-1979\/","title":{"rendered":"IEEE N320 1979"},"content":{"rendered":"
New IEEE Standard – Active. The essential performance parameters and general placement for monitoring the release of radionuclides associated with a postulated serious accident at a reactor facility are defined for various types of instrumentation. The predominant consideration in the assessment of radiation emergencies is the measurement of fission products made promptly enough to permit timely emergency decisions. This standard does not specify which of the instruments or systems are required, nor does it consider the number or specific locations of such instruments. This standard also does not address single failure criteria associated with nuclear safety instrumentation. You will receive an email from Customer Service with the URL needed to access this publication online.<\/p>\n
PDF Pages<\/th>\n | PDF Title<\/th>\n<\/tr>\n | ||||||
---|---|---|---|---|---|---|---|
6<\/td>\n | 1. Scope 1.1 Introduction <\/td>\n<\/tr>\n | ||||||
7<\/td>\n | 2. Definitions 3. References <\/td>\n<\/tr>\n | ||||||
8<\/td>\n | 4. General Consideration for Emergency Instrumentation 4.1 Instrumentation for Monitoring Emergency Conditions within the Reactor Facility <\/td>\n<\/tr>\n | ||||||
9<\/td>\n | 4.2 Instrumentation at or near a Reactor Facility for Assessing a Radioactive Material Release Re… 4.3 Instrumentation at a Distance from a Reactor Facility for Assessing the Radioactive Material … 5. Criteria for Radiological Instrumentation Systems <\/td>\n<\/tr>\n | ||||||
10<\/td>\n | 5.1 5.2 5.3 5.4 5.5 5.6 5.7 5.8 <\/td>\n<\/tr>\n | ||||||
11<\/td>\n | 5.9 5.10 5.11 5.12 5.13 5.14 5.15 <\/td>\n<\/tr>\n | ||||||
12<\/td>\n | 5.16 5.17 5.18 5.19 5.20 6. Systems for Monitoring Conditions within the Reactor Facility 6.1 Containment Monitoring Systems for Radioactive Noble Gases <\/td>\n<\/tr>\n | ||||||
13<\/td>\n | 6.2 Containment Monitoring Systems for Airborn Radiohalogens and Particulates <\/td>\n<\/tr>\n | ||||||
14<\/td>\n | 6.3 Systems for Monitoring Exposure Rate within the Reactor Facility <\/td>\n<\/tr>\n | ||||||
15<\/td>\n | 7. Instrumentation Systems for Detecting and Quantifying the Release to the Environs 7.1 Plume Detection 7.2 Stack Effluent Monitoring System 8. Installed Systems for Monitoring Conditions in the Environs 8.1 Air Monitoring <\/td>\n<\/tr>\n | ||||||
16<\/td>\n | 8.2 Exposure Rate Monitoring 9. Portable Instrumentation 9.1 Rate Survey Instruments <\/td>\n<\/tr>\n | ||||||
19<\/td>\n | 9.2 Portable Air Samplers 9.3 Direct Reading Dosimeters <\/td>\n<\/tr>\n | ||||||
20<\/td>\n | 9.4 Personal Alarm Dosimeters 10. Bibliography <\/td>\n<\/tr>\n<\/table>\n","protected":false},"excerpt":{"rendered":" American National Standard Performance Specifications for Reactor Emergency Radiological Monitoring Instrumentation<\/b><\/p>\n |