Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The Power-Cooling-Mismatch (PCM) Test, PCM-1 was conducted in the Power Burst Facility (PFB) in March of 1978. The PCM Test Series is being conducted at the Idaho National Engineering Laboratory by EG and G Idaho, Inc., under contract to the USNRC and is designed to characterize the behavior of nuclear fuel rods operating under conditions of high power or low coolant flow or both leading to departure from nucleate boiling. The PCM-1 test was performed to provide in-pile data for a ''worst case'' PCM incident. The objective of this experiment was to study the behavior of a single pressurized water reactor (PWR) fuel rod subjected to a high-power and low flow environment which would result in cladding failure at full power. The ''worst case'' conditions established for the experiment consisted of a rod peak power of 78.7 kW/m and a coolant mass flux of 1356 kg/s.m2. Fuel temperatures at the stipulated operating conditions were such that a significant volume of molten fuel was present when failure occurred which produced a high probability of molten fuel-coolant interaction (MFCI) with the possibility of a vapor explosion.
Fuel Rod Failure During Film Boiling (PCM-1 Test in the PBF). [PWR].
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The Power-Cooling-Mismatch (PCM) Test, PCM-1 was conducted in the Power Burst Facility (PFB) in March of 1978. The PCM Test Series is being conducted at the Idaho National Engineering Laboratory by EG and G Idaho, Inc., under contract to the USNRC and is designed to characterize the behavior of nuclear fuel rods operating under conditions of high power or low coolant flow or both leading to departure from nucleate boiling. The PCM-1 test was performed to provide in-pile data for a ''worst case'' PCM incident. The objective of this experiment was to study the behavior of a single pressurized water reactor (PWR) fuel rod subjected to a high-power and low flow environment which would result in cladding failure at full power. The ''worst case'' conditions established for the experiment consisted of a rod peak power of 78.7 kW/m and a coolant mass flux of 1356 kg/s.m2. Fuel temperatures at the stipulated operating conditions were such that a significant volume of molten fuel was present when failure occurred which produced a high probability of molten fuel-coolant interaction (MFCI) with the possibility of a vapor explosion.
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The Power-Cooling-Mismatch (PCM) Test, PCM-1 was conducted in the Power Burst Facility (PFB) in March of 1978. The PCM Test Series is being conducted at the Idaho National Engineering Laboratory by EG and G Idaho, Inc., under contract to the USNRC and is designed to characterize the behavior of nuclear fuel rods operating under conditions of high power or low coolant flow or both leading to departure from nucleate boiling. The PCM-1 test was performed to provide in-pile data for a ''worst case'' PCM incident. The objective of this experiment was to study the behavior of a single pressurized water reactor (PWR) fuel rod subjected to a high-power and low flow environment which would result in cladding failure at full power. The ''worst case'' conditions established for the experiment consisted of a rod peak power of 78.7 kW/m and a coolant mass flux of 1356 kg/s.m2. Fuel temperatures at the stipulated operating conditions were such that a significant volume of molten fuel was present when failure occurred which produced a high probability of molten fuel-coolant interaction (MFCI) with the possibility of a vapor explosion.
Behavior of Defective PWR Fuel Rods During Power Ramp and Film Boiling Operation
Author: Douglas W. Croucher
Publisher:
ISBN:
Category : Nuclear fuel rods
Languages : en
Pages : 44
Book Description
Publisher:
ISBN:
Category : Nuclear fuel rods
Languages : en
Pages : 44
Book Description
Behavior of a Failed Fuel Rod During Film Boiling Operation. [PWR].
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
A single rod power-coolant-mismatch test (Test PCM-1) was conducted in the Power Burst Facility to evaluate the behavior of a pressurized water reactor (PWR)-type fuel rod subjected to film boiling operation at high power for a time exceeding that resulting in rod failure. The mechanisms of rod failure, the test rod response following failure, and the consequences of operation with a large molten fuel radius following fuel rod failure were investigated through destructive and nondestructive examination.
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
A single rod power-coolant-mismatch test (Test PCM-1) was conducted in the Power Burst Facility to evaluate the behavior of a pressurized water reactor (PWR)-type fuel rod subjected to film boiling operation at high power for a time exceeding that resulting in rod failure. The mechanisms of rod failure, the test rod response following failure, and the consequences of operation with a large molten fuel radius following fuel rod failure were investigated through destructive and nondestructive examination.
Nuclear Fuel Rod Behavior During Normal and Abnormal Operating Conditions-results of Test PR-1
Author:
Publisher:
ISBN:
Category : Nuclear fuel claddings
Languages : en
Pages : 72
Book Description
Publisher:
ISBN:
Category : Nuclear fuel claddings
Languages : en
Pages : 72
Book Description
Energy Research Abstracts
Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 1696
Book Description
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 1696
Book Description
Fuel Rod Failure as a Consequence of Departure from Nucleate Boiling Or Dryout
Author: Robert Van Houten
Publisher:
ISBN:
Category : Fuel burnup (Nuclear engineering)
Languages : en
Pages : 48
Book Description
Publisher:
ISBN:
Category : Fuel burnup (Nuclear engineering)
Languages : en
Pages : 48
Book Description
Monthly Catalog of United States Government Publications
Author: United States. Superintendent of Documents
Publisher:
ISBN:
Category : Government publications
Languages : en
Pages : 1710
Book Description
February issue includes Appendix entitled Directory of United States Government periodicals and subscription publications; September issue includes List of depository libraries; June and December issues include semiannual index
Publisher:
ISBN:
Category : Government publications
Languages : en
Pages : 1710
Book Description
February issue includes Appendix entitled Directory of United States Government periodicals and subscription publications; September issue includes List of depository libraries; June and December issues include semiannual index
Government Reports Annual Index
Author:
Publisher:
ISBN:
Category : Research
Languages : en
Pages : 1032
Book Description
Sections 1-2. Keyword Index.--Section 3. Personal author index.--Section 4. Corporate author index.-- Section 5. Contract/grant number index, NTIS order/report number index 1-E.--Section 6. NTIS order/report number index F-Z.
Publisher:
ISBN:
Category : Research
Languages : en
Pages : 1032
Book Description
Sections 1-2. Keyword Index.--Section 3. Personal author index.--Section 4. Corporate author index.-- Section 5. Contract/grant number index, NTIS order/report number index 1-E.--Section 6. NTIS order/report number index F-Z.
Zirconium in the Nuclear Industry
Author:
Publisher: ASTM International
ISBN:
Category :
Languages : en
Pages : 490
Book Description
Publisher: ASTM International
ISBN:
Category :
Languages : en
Pages : 490
Book Description
Zirconium in the Nuclear Industry
Author: D. Franklin
Publisher: ASTM International
ISBN: 9780803107540
Category : Business & Economics
Languages : en
Pages : 516
Book Description
Publisher: ASTM International
ISBN: 9780803107540
Category : Business & Economics
Languages : en
Pages : 516
Book Description