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BS ISO 18077:2018

Superseded

Superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

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superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

Reload startup physics tests for pressurized water reactors

Available format(s)

Hardcopy , PDF

Superseded date

13-12-2022

Language(s)

English

Published date

23-04-2018

Foreword
Introduction
1 Scope
2 Normative references
3 Terms and definitions
4 Relation to other standards
5 Physics test program and selection criteria
6 Test method requirements
7 Requirements of this document
Annex A (informative) - User's guide
Bibliography

Pertains to the reactor physics tests that are performed following a refuelling or other core alteration of a PWR for which nuclear design calculations are required.

This document applies to the reactor physics tests that are performed following a refuelling or other core alteration of a PWR for which nuclear design calculations are required. This document does not address the physics test program for the initial core of a commercial PWR1.

This document specifies the minimum acceptable startup reactor physics test program to determine if the operating characteristics of the core are consistent with the design predictions, which provides assurance that the core can be operated as designed. This document does not address surveillance of reactor physics parameters during operation or other required tests such as mechanical tests of system components (for example the rod drop time test), visual verification requirements for fuel assembly loading, or the calibration of instrumentation or control systems (even though these tests are an integral part of an overall program to ensure that the core behaves as designed).

This document assumes that the same previously accepted analytical methods are used for both the design of the reactor core and the startup test predictions. It also assumes that the expected operation of the core will fall within the historical database established for the plant and/or sister plants.

When major changes are made in the core design, the test program should be reviewed to determine if more extensive testing is needed. Typical changes that might fall in this category include the initial use of novel fuel cycle designs, significant changes in fuel enrichments, fuel assembly design changes, burnable absorber design changes, and cores resulting from unplanned short cycles. Changes such as these may lead to operation in regions outside of the plant\'s experience database and therefore may necessitate expanding the test program.

1 The good practices discussed in this document should be considered for use in the physics test program for the initial core of a commercial PWR. One test that provides useful information (without additional test time) is the hot-zero-power to hot-full-power reactivity measurement.

Committee
NCE/3
DevelopmentNote
Supersedes 17/30337927 DC. (05/2018)
DocumentType
Standard
Pages
38
PublisherName
British Standards Institution
Status
Superseded
SupersededBy

Standards Relationship
ISO 18077:2018 Identical

ANS 19.5 : 1995 REQUIREMENTS FOR REFERENCE REACTOR PHYSICS MEASUREMENTS
ANS 3.1 : 2014 SELECTION, QUALIFICATION, AND TRAINING OF PERSONNEL FOR NUCLEAR POWER PLANTS
ANS 3.2 : 2012(R2017) MANAGERIAL, ADMINISTRATIVE, AND QUALITY ASSURANCE CONTROLS FOR THE OPERATIONAL PHASE OF NUCLEAR POWER PLANTS
ANS 19.4 : 2017 A GUIDE FOR ACQUISITION AND DOCUMENTATION OF REFERENCE POWER REACTOR PHYSICS MEASUREMENTS FOR NUCLEAR ANALYSIS VERIFICATION
ANS 19.11 : 2017 CALCULATION AND MEASUREMENT OF THE MODERATOR TEMPERATURE COEFFICIENT OF REACTIVITY FOR PRESSURIZED WATER REACTORS
ANS 19.6.1 : 2011(R2016) RELOAD STARTUP PHYSICS TESTS FOR PRESSURIZED WATER REACTORS

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