Published 1996 | Version v1
Report Open

Investigations on the inadvertent power increase in a PHWR as ASSET experience

Creators

  • 1. Operating Plants Safety Div., Atomic Energy Regulatory Board, Mumbai (India)

Description

Investigations were carried out using the ASSET methodology to find out the root cause of an incident involving inadvertent increase in reactor power in the Unit 1 of Narora Atomic Power Station (NAPS) in India. NAPS is a twin Unit, 220 MWe PHWR based power station. On December 4, 1992, when NPAS Unit 1 was operating at 130 MWe, the reactor power increased steadily on its own and touched 147 MWe, over a period of 14 minutes. The set (demand) power of the triplicated reactor regulating system had increased on its own and in turn has made the reactor to operated at higher power. The power was brought down to 120 MWe by manual intervention. Since adequate system related data during the incident was not available, laboratory studies were carried out using computer simulations for the various process disturbances which could affect the reactor regulating system, for establishing the causes of the event. 4 figs

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Part of:
Report of the technical committee meeting on 1996 annual workshop on ASSET experience

Additional details

Publishing Information

Imprint Title
Report of the technical committee meeting on 1996 annual workshop on ASSET experience
Imprint Pagination
209 p.
Journal Page Range
p. 79-94.
Report number
IAEA--J8-TC-871.4

Conference

Title
Technical committee meeting on 1996 annual workshop on ASSET experience.
Dates
25-27 Jun 1996.
Place
Vienna (Austria).

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
28055376
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
INDIA; INSTABILITY; PHWR TYPE REACTORS; POWER; REACTOR SAFETY; SAFETY ANALYSIS; VARIATIONS
Descriptors DEC
ASIA; DEVELOPING COUNTRIES; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; REACTORS; SAFETY

Optional Information