Published February 1993 | Version v1
Report Open

Analysis of decay heat removal by natural convection in PFBR

  • 1. Nuclear Systems Division, Indira Gandhi Centre for Atomic Research, Kalpakkam (India)

Description

PFBR is a 500 MWe, 1200 MWt pool type LMFBR. In order to assure reliable decay heat removal, four totally independent Safety Grade Decay Heat Removal Systems (SGDHRS) which removes heat directly from the hot pool, is provided. Each of the SGDHRS comprises of a hot pool dipped decay heat exchanger (DHX), a sodium - air heat exchanger (AHX) at a suitable elevation and associated piping and circuits. This paper brings out the step by step approach that have been taken to decide on the preliminary sizing of the SGDHRS components, and static and transient analysis to assess the adequacy of the Decay Heat Removal capacity of the SGDHRS during the worst of the foreseen design basis conditions. The maximum values the important safety related temperatures viz., clad hotspot, hot pool top surface, reactor inlet, fuel subassembly outlets etc., would reach, can be obtained only through a comprehensive transient analysis. In order to get quick and reasonably meaningful results, one dimensional thermal-hydraulics models for the core, hot and cold pools, IHX, DHX, AHX and various pipings were developed and a code DHDYN formulated. With this a total power failure situation followed by initiations of DHR half an hour later was studied and the results revealed the following: (i) clad hotspot temperature in the in-vessel stored spent fuel subassemblies could be held below 800 deg. C only if primary sodium flow through these subassemblies are increased up to three times the originally allocated flow in the design, (ii) hotpool top zone temperature reaches 572 deg. C, (iii) reactor inlet temperature reaches 482 deg. C, (iv) the hot pool top zone temperature cools down to 450 deg. C in about 25 h. Thus these results satisfactorily established the adequacy of the sizing and the capability of the SGDHRS. DHDYN code is also used to study the RAMONA water experiments conducted in Germany. Initial results available has brought out the conservative nature of the DHDYN predictions as compared to the experimental results. (author)

Files

31040793.pdf

Files (214.6 kB)

Name Size Download all
md5:57f507a03a0debc5ea306d03719492f1
214.6 kB Preview Download
Part of:
Specialists' meeting on evaluation of decay heat removal by natural convection

Additional details

Publishing Information

Imprint Title
Specialists' meeting on evaluation of decay heat removal by natural convection
Imprint Pagination
158 p.
Journal Page Range
p. 135-145
Report number
IWGFR--88

Conference

Title
IAEA-IWGFR specialists' meeting on evaluation of decay heat removal by natural convection
Dates
22-23 Feb 1993
Place
Oarai, Ibaraki (Japan)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
31040793
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Numerical Data
Descriptors DEI
AFTER-HEAT REMOVAL; COMPARATIVE EVALUATIONS; D CODES; EXPERIMENTAL DATA; FLOW RATE; FUEL ASSEMBLIES; HOT SPOTS; IN-VESSEL HEAT EXCHANGERS; NATURAL CONVECTION; POOL TYPE REACTORS; REACTOR SAFETY; SODIUM; THERMAL ANALYSIS; TRANSIENTS
Descriptors DEC
ALKALI METALS; COMPUTER CODES; CONVECTION; DATA; ELEMENTS; ENERGY TRANSFER; EVALUATION; HEAT EXCHANGERS; HEAT TRANSFER; INFORMATION; MASS TRANSFER; METALS; NUMERICAL DATA; REACTORS; REMOVAL; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
5 refs, 3 figs, 5 tabs