ALARM-B1: a computer program for boiling water reactor blowdown analysis
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment
Description
The digital computer program ALARM-B1 written in FORTRAN-IV for FACOM 230-75 is for analyzing thermodynamic and thermal-hydraulic phenomena of BWR during a large break LOCA. The outputs are pressure, core inlet flow and enthalpy which affect core heat transfer during transients. In ALARM-B1, the heat transfer from core to coolant during transients is not calculated, but it is given as inputs. ALARM-B1 solves integral forms of fluid conservation and state equations for user-defined volumes (nodes) which are treated as one-dimensional homogeneous elements with interconnecting flow paths (junctions). The numbers of nodes and junctions and their initial fluid conditions are given as inputs. The program is of a variable dimension so there are no limits to the numbers of nodes and junctions. (auth.)
Availability note (English)
MF available from INIS under the Report Number.Files
9350438.pdf
Files
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Additional details
Publishing Information
- Imprint Pagination
- 41 p.
- Report number
- JAERI-M--6968
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 9350438
- Subject category
- S99: GENERAL AND MISCELLANEOUS;
- Descriptors DEI
- A CODES; BLOWDOWN; BWR TYPE REACTORS; FLOW MODELS; FRICTION; HYDRODYNAMICS; LOSS OF COOLANT; MANUALS; PRESSURE DROP; THERMODYNAMICS; TWO-PHASE FLOW
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; DOCUMENT TYPES; FLUID FLOW; FLUID MECHANICS; MATHEMATICAL MODELS; MECHANICS; REACTOR ACCIDENTS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS