Author: S. L. Davidson
Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 130
Book Description
Thermal Analysis of Type 3 Elements in the SM-1, SM-1A and PM-2A Cores
Author: S. L. Davidson
Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 130
Book Description
Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 130
Book Description
Thermal Analysis of Type 3 Elements in the SM-1, SM-1A and PM-2A Cores
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
A steady state and transient thermal analysis was performed on the Type 3 replacement cores for the SM-1, SM-lA, and PM-2A plants. The fundamental criterion for acceptable thermal design is the minimum departure from nucleate boiling ratio (DNBR). The minimum design DNBR at design power conditions and scram power conditions for concurrent transient and steady state analyses is currently specified at 1.5. The steady state thermal analysis indicated that the SM-1 Tyne 3 core will operate safely at design conditions of 10.77 Mw and scram power of 13.45 Mw with minimum DNBR's above 1.5. Stationary elements in some peripheral core positions experience local nucleate boiling. The steady state thermal analysis indicated that the SM-lA Type 3 core will operate safely at design conditions of 20.2 Mw and scram power of 24.2 Mw with minimum DNBR's above 1.5. At scram power conditions a minute amount of local nucleate boiling in the hot channel was evident at the exit end of the most critical control rod and stationary element. Results of the thermal analysis indicated that the PM-2A Type 3 core will operate safely at design conditions of 10.0 Mw and scram power of 12.0 Mw with minimum DNBR's greater than 1.5. The analysis of all Type 3 cores showed they are safe during the early critical period (first 3 sec) of a loss of low transient. The corresponding minimum DNBR produced is 1.96 in the SMlA Tyne 3 core at the peak power level (scram power level) with the scram mechanism inoperative. Since this minimum DNBR occurs under the severest conditions and the minimum DNBR produced is greater than the design criteria of 1.50, all Type 3 cores are considered thermally safe. Under similar conservative conditions the SM-1 Type 3 core has a minimum loss of flow transient DNBR of 4.08 and the PM-2A Type 3 core has a minimum loss of flow transient DNBR of 4.59. At nominal power levels the SM-1 and SMlA Type 3 cores indicated local nucleate boiling in the hot channel while the PM-2A Type 3 core indicated no local nucleate boiling. At the scram power level all Type 3 cores indicate steady state local nucleate boiling in the hot channels. However, only the SM-IA Type 3 core indicated any bulk nucleate boiling in the hot channel during the first 5 sec of the loss of flow accident. In the evaluation of the SM-1 Type 3 core it was determined that increasing the flow coastdown time or scramming the reactor due to reduced flow does not appreciably affect the minimum DNBR but helps to impede the bulk fluid temperature rise during the loss of flow transient. (auth).
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
A steady state and transient thermal analysis was performed on the Type 3 replacement cores for the SM-1, SM-lA, and PM-2A plants. The fundamental criterion for acceptable thermal design is the minimum departure from nucleate boiling ratio (DNBR). The minimum design DNBR at design power conditions and scram power conditions for concurrent transient and steady state analyses is currently specified at 1.5. The steady state thermal analysis indicated that the SM-1 Tyne 3 core will operate safely at design conditions of 10.77 Mw and scram power of 13.45 Mw with minimum DNBR's above 1.5. Stationary elements in some peripheral core positions experience local nucleate boiling. The steady state thermal analysis indicated that the SM-lA Type 3 core will operate safely at design conditions of 20.2 Mw and scram power of 24.2 Mw with minimum DNBR's above 1.5. At scram power conditions a minute amount of local nucleate boiling in the hot channel was evident at the exit end of the most critical control rod and stationary element. Results of the thermal analysis indicated that the PM-2A Type 3 core will operate safely at design conditions of 10.0 Mw and scram power of 12.0 Mw with minimum DNBR's greater than 1.5. The analysis of all Type 3 cores showed they are safe during the early critical period (first 3 sec) of a loss of low transient. The corresponding minimum DNBR produced is 1.96 in the SMlA Tyne 3 core at the peak power level (scram power level) with the scram mechanism inoperative. Since this minimum DNBR occurs under the severest conditions and the minimum DNBR produced is greater than the design criteria of 1.50, all Type 3 cores are considered thermally safe. Under similar conservative conditions the SM-1 Type 3 core has a minimum loss of flow transient DNBR of 4.08 and the PM-2A Type 3 core has a minimum loss of flow transient DNBR of 4.59. At nominal power levels the SM-1 and SMlA Type 3 cores indicated local nucleate boiling in the hot channel while the PM-2A Type 3 core indicated no local nucleate boiling. At the scram power level all Type 3 cores indicate steady state local nucleate boiling in the hot channels. However, only the SM-IA Type 3 core indicated any bulk nucleate boiling in the hot channel during the first 5 sec of the loss of flow accident. In the evaluation of the SM-1 Type 3 core it was determined that increasing the flow coastdown time or scramming the reactor due to reduced flow does not appreciably affect the minimum DNBR but helps to impede the bulk fluid temperature rise during the loss of flow transient. (auth).
APAE
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 156
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 156
Book Description
Half-year Summary Report, Army Pwr Support and Development Program
Author:
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 156
Book Description
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 156
Book Description
Nuclear Science Abstracts
Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 1300
Book Description
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 1300
Book Description
Nuclear Science Abstracts
Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 1528
Book Description
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 1528
Book Description
Monthly Catalog of United States Government Publications
Author:
Publisher:
ISBN:
Category : Government publications
Languages : en
Pages : 1284
Book Description
Publisher:
ISBN:
Category : Government publications
Languages : en
Pages : 1284
Book Description
Monthly Catalog of United States Government Publications, Cumulative Index
Author: United States. Superintendent of Documents
Publisher:
ISBN:
Category : United States
Languages : en
Pages : 1284
Book Description
Publisher:
ISBN:
Category : United States
Languages : en
Pages : 1284
Book Description
Keywords Index to U.S. Government Technical Reports
Author: United States. Department of Commerce. Office of Technical Services
Publisher:
ISBN:
Category : Government publications
Languages : en
Pages : 990
Book Description
Publisher:
ISBN:
Category : Government publications
Languages : en
Pages : 990
Book Description
Keywords Index to U.S. Government Technical Reports (permuted Title Index).
Author: United States. Department of Commerce. Office of Technical Services
Publisher:
ISBN:
Category : Government publications
Languages : en
Pages : 860
Book Description
Publisher:
ISBN:
Category : Government publications
Languages : en
Pages : 860
Book Description